ML20148Q433
| ML20148Q433 | |
| Person / Time | |
|---|---|
| Issue date: | 01/15/1981 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | |
| References | |
| ACRS-T-0814, NUDOCS 8101220324 | |
| Download: ML20148Q433 (197) | |
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Ir2 the Matter of: ADVISORY COMMITTEE ON REACTOR SAFEGUARDS .
SUBCOMMITTEE ON EMERGENCY CORE COOLING SYSTEMS emme.
January 15, 1981 PAGES: 295 - 490 DATr-J Ay; Albuquerque, New Me:.xico cn 4N J
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NUCLEAR REGULATORY COMMISSION ;
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l 3lI In re: .:
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4l Meeting of the Advisory Committee :
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. j 8 Teseque Room, 4 i The Regent Hotel, l 9i Albuquerque, New Mexico, '
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.y 10 l Thursday, January 15, 1981 i '
E I II y The meeting was reconvened, pursuant toadjournment,l 12 I 2 at 8:?0 o ' clock a.m. , Milton Plessett presiding.
A 5 j 13 l PRESENT:
3 14 E DE. MILTON PLESSETT, Chairman, Subecmmittee.
E g 15l; DAVID WARD, Member, Advisory Committee on Reactor 16 {
Safeguards.
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W. MATHIS, Member, Advisory Committee on Reactor y Safeguards. ;
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, ;:: ! HAROLD ETHERINGTON, Member, Advisory Cc=mittee on ;
{ j9 Reactor Safeguards. I <
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20 ' P. 30ENNERT, Staff Representative. 1 21 DR. I. CATTCN, Consultant, Advisory Ccemittee on
! Reactor Safeguards, i 22 ,
J. LIENHARD, Censultant, Advisory Cc=mittee on fi 23 Reactor Safeguards. ,
24 4
DR. Z. ZUDANS, Consultant, Adviscry Ccemittee on g Reactor Safeguards. l
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I DR. T. WU, Consultant, Advisory Ccemittee on j l .
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1' DR. A. ACOSTA, Consultant, Advisory Committee on ,\
Reactor Safeguards.
I DR. T. THEOFANOUS, Consultant, Advisory Committee j 3 Reactor Safeguards. l l
4 DR. Y. CHEN, Senior Consultant, Advisory Committae !
i on Reactor Safeguards.
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- it i j i $ 7 Dr. Harold Sullivan . . . . . . . . . . 298 ~
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j 8 Larry E. Hochreiter . . . . . . . . . . 322
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- ! 9 g Jerry Burnette . . . . . . . . . . . . . . . . . 379 .
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298 l 1 PR0CEEDINGS 2l CHAIRMAN PLESSETT: We will reconvene.
3 We are going to have to stay on schedule today or.e 4l way or the other, because of the problems of travel, so I c 5ll hope you understand if I shut someone off. This refers to 9 ,
j 6' consultants, ac well as the speakers, so that we can stay on ,
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I schedule. i 2 ,
s 8! Let us go right into the agenda. Harold is going J !
9I to give us an overview on the separate effects and model de-
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3 I y 10 l velopment program.
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s STATEMENT OF DR. HAROLD SULLIVAN, d 12 E OVERVIEW OF SEPARATE EFFECTS AND MODCL DEVELOPMENT
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- 13 i j DR. SULLIVAN: The program this morning is an over-E 14 '
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view of the separate effects and model development program 9 15 t j and the experimental programs.
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$ ! We have chosen three of the largest experimental i H 17 i
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! l Those are the FLECHT program,and the contractors 20 are here; the SSTF, the Steam Sector Test Facility; and the 21 l k TLTA.
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As you know, we have an upgrade program for TLTA. I 23 'l That upgrade will be also discussed.
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! Starting now with the model development program, 25 , ,
I would like to cover four main areas. There is the model ALDERSON REPORTING COMPANY, INC.
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development program, itself, and I will discuss each of the 2l contracts. There is the instrumentation for inadequate core '
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3l c ooling . We have specifically in one area the liquid level 4 inside of the vessel.
I y 5 Also, there is the tuo phase performance of pumps n ,
j 6 which is an update of the meeting in Idaho.
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I E What I will try to be doing is just to update some'
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8l recent developments on that. We have tried to answer some- l dx i
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}e 9 I of the questions that you have asked in Idaho. i
> 10 Then to conclude, there is the THT7 program at II Ock Ridge.
l" 12 g i Looking at the model development program first, 5 d 13
% g the objectives, those of the program, are to obtain thermal z t
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g on phenomena that are occurring.
f 16 What we are doing is using some small scale exper-R 17 .
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j 19 imental programs and trying to understand the phenomena.
20 l l We are also looking at that data to develop =odels and cor-21 l relations from not only the large experimental programs but 22 l also from the small scale experiments that we have done.
23 m Then the last cbjective is to provide any advice
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to NRR. It also helps to guide our large experimental pro-25j c grams in their research that they are doing.
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1 The background of that program or the model devel-2l opment program is to provide a link between the thermal hy-3' draulic tests and the code development, to provide a link 4
between our separate effects and the integral systems ' e::-
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j 6> Pre-TMI we were looking at the large break LCCA. ,
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6 7 Post TMI we were looking at the small break and the opera-i M ! .
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cooling and fluid / solid interactions and the station black-5 13 out.
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y In the future, you will see the direction of that 5 15 ,
program shifting in that direction.
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$ : DR. MARK: What is fluid / solid? Is that corrosion?
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@ j DR. SULLIVAN: No. If we are looking in a degrad-c w 18 , .
g l ed core cooling, the worst case of degraded core cooling we t 19 l' 4 will be looking at trying to cool core that is slumped in 20 !
the center, so we are 1 coking at how to cool that. That is 21 part of that.
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3 Another part of that is the water hammer question 23l i which is that which came up in the last ACRS =eeting in Wash-24 i
] ington.
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- We are trying or going to egt to put together a i
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As 1! program which we are looking at, a number of fluid / solid ,
(V) 2 interaction problems.
3l l It probably is not very well named. "t covers a 4f variety of things, g 5l DR. ZUDANS: It is not in the hydraulic density.
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3 6l It is in the sense of local geometries or something like
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n j 8 DR. SULLIVAN: Yes.
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. Let us say the water hammer case, we are going to
'h 10 l look at the effect on the structure, itself, of having wa-
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13 DR. ZUDANS: That is what I call SFI, Fluid Struc-E 14 E tures Interaction. You call yours the same?
e 15 g DR. SULLIVAN: We have just lumped a lot of them 16 3 together and called them fluid / solid interactions.
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$ DR. CATION: That includes the degraded core cool-E 18
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E 19 A j DR. SULLIVAN: Yes. There are two main things.
20 I l One is that we are going to try to look at water haccer and 21 I :
the other is degraded core cooling and look at flows through 22 ! l
! solid rubble, part of the rubble beds where there is some of 23 '
the interaction of the fluid and the solid and the heat n
I transfer.
25 DR. CATTON: Isn 't there a program already in ;
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l place in degraded core cooling at Sandia under Kelber?. l 2' DR. SULLIVAN: The division between the work that 3i Kelber is doing and the work that we are doing is that there 4 is a very sharp distinction between those.
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When it melts through the lower grid plata, it 6
belongs to that, another of that severe accident phenomena. ,
E y 7l DR. CATTON: So your degraded core cooling will be ~
8 i a more structured thing? It won 't be dust a bunch of lit-a i 9
h~. tie small particles.
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j ; DR. SULLIVAN: Yes.
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l II l To look at some of the user need levels that we 12 l <
had, and I was just going to give you a brief overview of E 13 s some of the reasons that we are doing research in the areas 2 14 i y that we are doing, and also give you a background of why the 5 15 '
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separate effects programs that we have going, both the PWR 16 i 3 l and BWR, are in existence.
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came from Brian Sheron who wrote it. It was also fairly C 19 l.
A old in '79 in that it called for some blowdown heat trans-20 !
- fer work, some refill and reflood.
21 l i l You notice that the first two items of that are the l
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work that we are doing and the FIICHT program which Larry 23 l Hochreiter is going to present, it also shows the 20=3D of-j l 24 l j facts and the larger scale refill models.
25 j The PWR research is also here. That has driven ALDERSON REPORTING COMPANY,INC.
l 303 the 30 degree sector test and also some model development s 1:
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2 work in RPI and also the TATL program.
3 It was in the same user need, but it is now looked i
4I at in the small break area, that is, they wanted to look at I
e 5i core uncovery. These are the last experiments that we have 9 !
j 6; run in THT? at Oak Ridge.
E i E 7! They also looked au steam generators and that cir -
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Now looking at the model development programs, and ;
20 what I will try to go through just quickly are some of the 21i results that have come out of these, mostly university pro-l 22 !
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I 23 MIT, as you know, has given us a lot of thermal
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hydraulic data in the reflood Srea. They have also done some 25 j
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steam generator work.
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Stan presented some results from that yesterday 1
2i in his code assessment when he was talking about code as-3l sessment. l l
4* What we have done is looked at steam generators in a 5l two phase flow and the behavior of the tubes, themselves, n !
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d 9 Northwestern has looked at condensation. They 5.
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are primarily looking at two parts. One is parallel flou II I condensation and spraying drops into a steam environment t
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looking at the condensation on those drops.
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$ I4 , sults are being used by several of the code development ef-e !
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The work is being used for the model development 20 l area and BWR 's. Lehigh,which is an ANL, and Argonne are 21 '
looking at the post CHF data. They are getting post 22 ]
CHF data and evaluation of correlations that have been de-23 velopment.
- As you will see, that work is going to be l 25 l ,, continued at Lehigh, and looking at a nonequilibrium on,e, l
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l 305 1- 1; correlation.
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We also think that the data is applicable to the 3
j early stages of degraded core cooling. The Sunnybrook ::ork I
i 4, is being done further. They are looking at measuring the g5 droplet distribution out of the upper course support place.'
3 6! The work was to support the 2D-3D program.
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dicated, the post CHF transfer work,. heat transfer work, O 5 will be centinual and we will be taking scme film, boiling 3
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a larger data base, from a large number of separate ef-21 fects and integral experiments.
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i The steam generator work is planned to be con-23 tinued. We are asking them to develop some techniques for 25 looking at noncondensible' gases, for detacting ncncondensibla gases, and to,look at the effect of those noncendensible gases I
- ALDERSON REPORTING COMP ANY, INC.
j 306 to develop models for the flow distribution and steam gener-1l 2 ators, and to incorporate the noncondensible gas effect in 3l those =odels.
4 The phase distribution and separation work, we are g 5 planning on ecmpleting that at RPI. We would lika to devel-e 3 6 op a model based on the work that 1,ahey has done. We would g
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^j l like to complete the parallel instability problem in paral- ' j j
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. We are scoping some effects of failures in jet I- 10 g pumps, how large a break has to be before we can 't reflood II the core.
12 l It is a recent addition to that program. The BWR E
s 13;i thermal hydraulic work is an RFP that is to be let out. It
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- i will look at the thermal hydraulic instabilities and also to E i e 15 9
! obtain some drif t flux data.
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$ We are planning to complete the work at Morth-p 17 ' .
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I 19 A l dis tr ibution.
l 20 i The natural circulation work at Purdue is to look l 21 l at the heat transfer in a bundle during natural circulations 22 o low flows. [
23 $3.
We are also jus;t+ starting to work on a degraded core cooling heat transfer R7?, which is to be let cut. We 25 ,
'I 4, will be looking at the heat transfer and the fluid flow in a ALDERSON REPORTING COMPANY, INC.
! 307 1
degraded core situation.
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Y- # 2l This will be from a small amount of blockage all l
l 3l the way to fairly large siumps in the core, itself, i
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4[ That completes the bundle davelopment. If there i i l c 5l are no questions, I will proceed on to the inadaquata core n
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" 7al DR MARK: Along the way, you mentioned the ATWS -
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!' $ 9I at ATWS? I thought ATWS was studied for 10 years and the g" 10 il cost benefit analysis published of the benefits doing also
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5 II ! whatever is to be done. Does i: :nly now come to research?
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12 DR. SULLIVAN: The research program is loching at 4
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s 5 the flow through relief valves.
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. y ported program of fairly high pressures.
I 5 15 We will be locking at
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! 16 ' these medels that are Seing develeped.
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- l a Another question is the heat transfer in the core.
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5 18 g i If you go and have a return to high power levels, CHF at
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A very high pressures, the heat transfer at very high pres-I 20 sures, those are the ewo outstanding questions that we see.
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! We have not developed a program yet, but those 22 i
' are two of the outstanding questions.
I 23 DR. MARK: That is an afterthought after the rule l
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24 making?
25 a DR. SULLIVAN: Yes.
0 ll ALDERSON REPORTING COMPANY, INC.
l 308 I
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I If we could turn our attention to the instrumenta-2 tion to detect inadequate core cooling, the objective of the 3'
program is to look for some instrumentation that you can get 4
in a nonambiguous indication of the liquid level in the re-l 2 0 actor core.
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f6 When you first say that, it does not sound too bad. ,
E 7' It is only when you start looking at a two phase situation 3 l E l M
ali where there is a defined interface and where in that inter- l 4 l l
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face a rod can be and still be cooled.
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j We are looking at perameters such as flow, equal-5 11
- ity. What do they have to be before you can actually cool 0 12 g ! the core? How do you detect the onset of that and give the 5 13 'I i operator some warning?
4 14 l g The research application is to assist :TRR in eval-9 15
@ ! uating the submittals of the vendors. We are doing very lim-T 16 !
3 ! ited research in the actual development of the instrumenta-d 17 E
- i, tion.
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E ; We only have one method that we are pursuing at I 19
A this time.
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We are also going to look at the TMI action plan. l 21 t There are a couple of cases that we would like to look at in l 22 l
the process monitoring instrumentation, and its performance d uring accident situations. l 24 l Those are the two main areas that will need ad-25 a d ress ing.
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1 The approach that we have now is to actually put V 2, vendor instrumentation into a test facility and get conform-3 ! itory data that predicts the onset of inadequate core cool-4! ing and to look at the definitions of what inadequate core j 5 cooling is.
2 6
4 The program that we have at Oak Ridge and Idaho,
- t 5 7 j we have built a heat thermocouple system. We are evaluating' s 1
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, 10 thermocouple, and the Oak Ridge heated thermocouple have been
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put into the TFTH loop and tests have been run.
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i q l The results indicate that it is a method that looks I3 l very positive, that it will be able to be used.
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y l We have also installed the Westinghouse Delta ?
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j system in the semiscale and we plan on starting testing in i
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- We have installed the EPRI Neutron Detection Sys-5 18 i g j tem in LOFr. That was used on L23. Those results are new C 19 '
A j being evaluated, I mean, L36. .
20 !
j We plan to include the Oak Ridge heated ther=o-21 i l couple system and semiscale and we also are looking at the 22 '
CE system. CE is evaluating where they would also like to 23 put their heated thermocouple system in the or and the semi-24 b scale.
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1 There is at least then one heated thermocouple l
ALDERSON REPORTING COMPANY, INC.
i 310 1: system that will be included in semiscale.
2! The last part of the effort '-
to cocrdinate the l
3i NRR test results with the submittals from the reacter ven-l 4l dors. They are due on January 1st.
e 5'I DR. CATTON: How well does the EPRI system work, E
j 6 do you know?
$ 7 DR. SULLIVAN: I really do not know. I am not 7.
j 8 sure who is doing the evaluation. It is either by Idaho,
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3 find out.
B g" 12 I DR. ZUDANS: Conceptually, how many different sys-4 I3 tems are you looking at'?
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E l DR. SULLIVAN: There is the heated thermocouple u I F 15 g i system.
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." 16 B I DR. ZUDANS: That is one.
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" 17 d ! DR. SULLIVAN: The Delta P system.
f I w 18 t DR. ZUDANS: That is two. -
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19 i j l DR. SULLIVAN: There is a new system which is being l 20 l supported by EPRI which is a microwave system. l 21l: Three.
DR. ZUDAM3:
22 '
DR. SULLIVAN. There is a new system which is t
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the neutron detection system. Then there is just using l; thermoccuples, themselves, and the heat of the metal to 25 j l show that you are in a steam environment.
l ALDERSON REPORTING COMPANY. INC.
1 311 l p L'4 1- Those are the major systems that I can recall
'N- l 2; right away.
I 3! MR. WARD: Are there any kinds of a conductivity 4 ' cell, a buoyancy system, a float sort of thing?
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DR. SULLIVAN: When the program first started, we n
j 6 did a survey of all of the systems that we thought were pos-s7 sible.
We considered the buoyancy system. We thought that '
7.
j 8 that was mechanically not reliable. You mentioned one more, e
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, MR. WARD: Conductivity.
E 5 10 DR. SULLIVAN: They just won 't stand the radiation
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m y 12 DR. CATTON: What about acoustic?
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g 13l. MR. WARD: I am not sure that that is right.
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I4l DR. SULLIVAN: We did not investigate that in de-E I g 15 g3ty,
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I g' 16 j MR. WARD: I know what I am saying, but the con-
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$ ductivity probe has been used at lower temperatures in fair-
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19 l j DR. SULLIVAN: Then we should probably look at 20 !
- that. The LOFT facility has the conductivity prebes in them.
l 21 1 j They have had some problems with them.
22 '
l They are a good research tool, an excellent re-23 search tool, but you have to be able to service them = ore eu
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a fairly frequent basis. I x_
25 l 1 MR WARD: This particular application is not ,
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I 2! DR. SULLIVAN: I would be interested now in find-i 3! ing out.
4! DR. CATION: What about the acoustic?
i n 5, DR. SULLIVAN: I think that it is sert of touchy w
j 6 situation. We were going to look at the development of that g .
$ 7' acoustical and maybe--I said it wrong. It is a microwave s-
- g 8 system. It is acoustics.
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9l DR. CATTON: I thought that it was the microwave s
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that was touchy.
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II l i DR. SULLIVAN: I remember that it was a microwave B
g 12 l system, but I don 't know what you mean by acoustics. It was I
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DR CATTON: But the microwave is a reflection of l
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DR. SULLIVAN: Yes, but we looked at that system 17 d -
and B.and W got interested in developing it. We did not 5 !
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industry was doing.
20 I DR. CATTON: It was not because bad that you did 21 i
! not list it?
t 22 i DR. SULLIVAN: No, but it certainly had its problems 23 '
We have a lot of development work that still is left to be j, done.
I
- 25) I don 't know, but were you at the =eeting in Idaho?
i ALDERSON REPORTING COMPANY. INC.
l' 311 F' 1 DR. CATTON: Yes.
7 V 2 DR. SULLIVAN: That was a good demonstration, but 3, when we tried to apply it it got difficult because of the
'4l steam environment, the window that was needed through the e 5 vessel. Those problems then got to be significant. We did n I f 6l test the glass and boron really worked on that glass.
Ti A 7 Now I would like to conclude with the THTF program.
l 8 in Oak Ridge. We have concluded the major experimental pro-e y 9 gram in November of this year. That was the testing in that.
5
$ 10 l It did address the licensing issues.
$ l 11 It also has given us some valuable data for code i::
y 12 assessment and correlation comparison.
O 4 V lw 13 The data can be used for Ap, We believe 5 14 that it is the onset of the degraded core cooling and, in E
j:: 15 ;
\
l particular, is the bundle film boiling experiments, and the j 16 uncovery and recovery experiments.
m I7 ' The plan is to produce the data reports in FYSO E \
l 18 with the uncertainty, and to put that data in the Idaho data E
g 19,I bank.
20 This gives you a little better understanding of 21 the experiments that have been run.
22 i There was a bundle uncovery/ recovery series. That 23 was run in February, j ; 24 ' There is a transition or a film boiling experi-25 l It was with upflow and with downflow.
ment.
ii
- I ALDERSON REPORTING COMPANY, INC.
1 314 1! We ran one double ended cold leg break and that I
l 2,l was to relate the results with the new bundle and the new i
3l ;
instrumentation back to the old bundle. The instrumentation 4' was not nearly as good in the old bundle as it was in the i
m 5! new. \
l A : '
s j 6+ We needed a cross-ccmparison test. We perfor=ed R
! 7l quasi-state bundle film boiling. test. Then there was bundle' l j 8I boil off recovery and uncovery series. Those were the last d i L d 9l experiments to be done. I
& l
@ 10 We are currently looking at the facility and the E
j 11 data that we have to see if there are any holes that we have a
12 g i left before we mothball the experimental facility.
! 13
! I g
I would like ta sav that the last tests that were z
I4 ;
je run in that facility were very good. We got some really good j
15 ' information.
f z
16 We got out of the large break where the instrumen-1 17 l
$" tation uncertainties were putting us into an area that we c 1 z 18 '
The data i new would not recondition the bundle very well. l
" I 19 '
j j that was produced, I consider that to be very good. i 20 l l I think that we will be seeing a lot more of that 21 I data in the future.
22 DR. CATTON: Did they get the void fraction bundle 23 '
system to work?
DR. SULLI7AN: Yes.
25.l 1
In fact, we have just seen scme data from them on ALDERSON REPORTING COMPANY, INC.
315 l where they traveled,in a detector system across grid plates pS~ j
\ / l 1
'- ' 2 so that you could get the density variation across the grid 3 plates. That is very interesting. 1 1
4 It is going to take a long time to try to inter-g H
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pret it, because of the effect of the grid plate, itself, i
a as you transfer the source.
- R \
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E 7 It has too much metal? -
DR. CATTON:
s 2 8 M DR. SULLIVAN: Yes, but it promises to be some vey e
9
)
useful data.
' 10 i DR. CATTON: Those instruments look to me like
=
5 11 g they are of a lot of interest. What is going to happen to
'i 12 i them? Are you going to try to do something like that on a E
(' 13 l semiscale maybe?
i ,
E 14 I
- d DR. SULLIVAN: A lot of the instrumentation that .
u 9 15 j was in that is duplicated in semiscale to some extent.
T 16 3 DR. CATTON: I am referring to the void fraction f
w 17 l in the instrument bundlas, f I w 18 ,
g DR. SULLIVAN: That instrumentation works the I 19 A , best in steady state transients, where you have transients 20 that are really transient conditions. The instru=entation l
21 is not really nearly as effective as in this last quasi 22 !
- steady state.
23 i DR. CATTON: So the sourcels small. I 24
[}#
(_j DR. SULLIVAN: Yes, and we are going to try to 25 )
. apply that, the instrumentation development work that we l ,
. ALDERSON REPORTING COMPANY, INC.
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have done there to other expdri= ental facilities.
2 DR. CATTON: To me, that kind of closas the pic-3 ture.
4l I am always bothered by inlet and cutlet in a ec=-
g 5 vi puter code and t.his seems to eliminate part of that.
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It would be worth, in my mind, a lot of work to -
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3 =ake it work elsewhere.
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8; J" i DR. SULLIVAN: Yes, we agree.
~ 9i '
Now looking at the large break results, the non-1 10 g equilibrium there in the heat boiling transfer, there were
=
2 11 g , nonequilibrium conditions in the bundle.
12 l j The equilibrium assumptions that we have made in 5 13 i , the past were not valid. The Dougall-Rosenhow correlation E 14 I y
} overpredicted the heat transfer in the bundle.
9 15 i
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The Groeneveld 5.7-5.9 TRAC 's related clearly well.
16
$ We are going to be looking at this a lot more deeply too and ,
d 17 5 ; this calendar over in this fiscal year.
5 18 I
- 5 l DR. CATTON: Will here there be an impact on Appen-t 19 {
A ; dix I because of the findings en the Dougall-Rosenhow equa- ,
20 l l tion?
21 !
DR. S*u1LIVAM: We think there vill be.
22 ' I i
i DR. CAITON: There are about two or three, if I !
23 remember. '
24 1 I
l h DR. SULLIVAN: About two, and the thing that we a n 25j j trying to do new is to make sure thzz: that data is well qualifi: ;
i ALDERSON REPORTING COMPANY. INC.
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317 79 1 before we start the comparisons with Dougall-Rosenhow. We
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have done some such work now.
f 3! We would also like to know what happened to how 4 the data that the CE sponsored obtaining is different from 5
g l the data that Oak Ridge has obtained.
H j 6 ; DR. CATTON: What is your procedure? What do you R -
$ 7 do7 8
DR. SULLIVAN: We are now qualifying the data for 4
9l the Oak Ridge facility. We are going back and looking at c I H 10 ' the bundle and the test conditions that produced the data
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that Dougall-Rosenhow came from to see if there is a basic i 12 ! difference.
I n t 13 l l3 A close look at it says that there is a basic dif-14 5 ference and we have to understand that.
=
0 15 g DR. CAITON: That is certainly true, but if you 16 i j
?
l conclude that your results are good, then you have that factor
" 17 '
$ , of two. What is your next step?
E 18 g DR. SULLIVAN: It is a licensing question.
I 19 -
A j DR. CAITON: You turn it over to licensing?
20 l Yes.
i DR. SULLIVAN: I 21 l i Now the time that CHF was comparable in both the, 22 !
rather the Cy was comparable in both the flat and the cosign 23 24j l]l power case, in the bundle uncovery and recovery e::periments, l
[
l V !i we noticed :: hat steam cooling is affected.
25 !
'l 3
It was an English unit: that is about seven to i
i ALDERSON REPORTING COMPANY, INC,
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1 1l thirty-three. The H was. i 2 The absorption of the steam was fairly signifi-3 cant too. We had to develop a model to account for that.
4 We used the Edwards' type model. It is a model g 5li that was developed at UCLA.
8 ; -
@ '6 i We also saw that Dittus-Boelter credicted the re- '
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g 8! ing hot walls and you used a then steam temperature, the d
9 j quench, the recovery part of the experiment, we noticed tha.
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' 10 j the quench rate was slower than the bundle in flooding rate.
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l II l That was fairly or very similar to the reflood h'
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data that was obtained at lower pressures.
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13 1 E The FY31 conclusion of the program would be to do
$ 14 6 i data evaluations. We would like to put out an uncertainty E
r 15 l j "
report on the data, but on certain parts of the data and i
16 I
$ to put that data in the data bank.
F 17
$ . sould like to now cover the last part of this E 18 g j which is the two phase pump performance. I think when we t 19 '
R l were in Idaho we had not received the one-fifth scale pump 20 !
data that the combustion and EPRI ran.
21I We have that now. We have explored the possibil-h 22] ity of doing some two phase pump performance and when we were 23 in Idaho it was with 3ingham-Willamette and then at chac tL=e 24 '
we indicated that the program was very expensive and we de-25 cided not to do that.
1 i ALDERSON REPORTING COMPANY, INC.
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l j i 319 fag i There is the possibility we have explorad with the '
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Italians and the Canadians, two possibilities. They wculd 3ll , like for us to join their effort in looking at the perform-4 l ance of pumps in two phase conditions. :
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- ' The Ontario hydro pump is very similar to our re- I
]g 6i actor cooling pump, but it is in a can do system so there ;
7l are some differences.
j i 8'
d Both of the pumps that we are looking at now are 9
full scale.
I 10 y It will look very similar to'the one that was at lII Bingham-Williamette. The applications of that, we still d 12 3 have the overspeed issue.
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i If the pumps are not connected to the turbines
$ 14 y l as a breaking system, the integrity of the pumps, which was 5 15 j brought up in the Idaho meeting and also the modeling of 16 3 ; the pumps in two phase conditions, and we are also interest- ,
" 17
$ ed in obtaining data of current versus void to help us use E 18 g j that as a trip mechanims on the pumps to see if that is a t 19 A valid treatment mechanism for the pumps to look at the pumps 20 l l on/ pumps off question.
21l h We did some work on an issue that was brought up. l 22 ; i i
I had forgotten who brought it up in Idaho. They wanted us 23 ' I to look to see if we,thcught the pumps would operate teo or !
O) t.
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- through a two phase transient.
25 , {
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We called several of the pump vendors. It was a 1'
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mixed feeling.
2 One pump vendor said that he thought that the pumps 3
j would operate. There is a vibration limit, a monitoring 4
limit on it, and he thought that that would be exceed and j 5 could cause the operator to actually shut the pumps off.
6i 5;
u This is very similar. to what happened in TMI.
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- 2 8 n
a j pump would, they never tested it, and it was not designed to d 9 ;i g i go through a two phase system.
- I h 10 g
That concludes my presentation on the bundle de-2 j 11l , velopment program and some of the questions that were brought 3
12 ll up in Idaho. I will try to answer those.
S I would like to now call on Larry Hochreiter if
$ 14 y l there are no questions. He would address the FLECHT-SEASET j 15 '
l program.
J 16 j G CHAIRMAN PLESSETI: Let me just make a remark, d 17 s ; Harold.
$ 18 l -
ij l We were asked if we could get this steam explosion
'?. 19 '
N l presentation in this mcrning. I just want to say that we 20 l will try to do that if we can get the people here, but it 1 21 i l
might come af ter Larry 's presentation. 1 22 '
Do you think your people will be here then?
23 l DR. SULLIVAN: I still do not see the guy from l 24 l NRC. I will need to call back and find out and to get them 25 j l to notify Sandia that they should be early also, i
ALDERSON REPORTING COMPANY. INC.
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, 1 CHAIRMAN PLESSETT: Larry, I guess it is your 2, turn.
3 DR. CHEN: . Mr. Chairman, may I ask a question?
4 CHAIRMAN PLESSEIT: All right.
e 5 Dr. Chen has a question.
8 3 6 DR. CHEN: In your presentation; I have not heard a :
$ 7 anything about the unitized test. Yesterday we mentioned -
s' j 8; about the semiscale for UHI. Do you know any way where we a i d 9 can find a bigger scale test facility for UHI tests so we 3
5 10 can have that?
5
$ II DR. SULLIVAN: The semiscale program has conducted a
f 12 a small break with UHI and one without.
(s_-)/ 5 j 13 We are now comparing those results. Are you ad-l14 dressing the area of UHI with large breaks?
e j= 15 DR. CHEN: The UHI with large breaks or small g 16 breaks. How are you comparing with the COBRA-TRAC process z
F 17 '
d then?
=
18 h DR. SULLIVAN: You remember in the presentation j yesterday there is a separate effects experiment that cov-20 l cred TRAC.
21 DR. CHEN: My question is though, to check the 22 !
l UHI water bypass, you need en integral system, integral test 23 '
facility?
24 ll4 t DR. SULLIVAN: Yes. CHI tests have been performed i
25 J in semiscale and I think there is one more of those UHI
! ALDERSON REPORTING COMPANY, INC,
I 322 1
experiments to be performed. We think we have a comparison, l 2l a tast without UHI and one with UHI now. We will be looking t
3lI cc that data.
4 The Japanese ran a UHI experiment. It was ROSA II.
i g 5 H
i CHAIRMAN PLESSETT: ROSA III, I think.
3 6 i DR. SULLIVAN: ROSA III, and we have that data. .
n R 7 i DR. CHEN: That has been criticed because that 3 8 A
heat transfer surface area, is it sensitive, are they going 9
g '
to run some more tests?
$ 10 I .
E
! DR. SULLIVAN: The semiscale facility has tried to 2 11 j address that heat transfer surface area question. They have 4 12 l
! put insulators in the downcomer. They are planting them and E 13 l E , putting them in upper portion of the vessel.
E
$ 14ll Also they have been putting in the lower plen'ic,
! 15 '
s so we have tried to address that question.
j 16 !
w Probably there is an excess of heat transfer in d 17 '
s i the facility yet.
E 18 ; .
2 l DR. CHEN: So you are going to conclude that we Cx 19 ,i M
j only have samiscale and ROSA?
20 1 i
CHAIRMAN PLESSETT: That is right.
21 I I
j DR. SULLIVAN: Yes. We have looked at putting the 22 '
UHI system in LOFT and the upper plenum is just not designed 23 or can stand the stresses of that.
24 STATEMENT OF LARRY E. HCCHREITER, l CVERVIEW AND RESULTS - WESTINGHOUSE ALDERSON REPORTING COMPANY. INC.
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1' MR. HCCHREITER: What I uculd like to do this 2 morning is to give you an overview of some of the results 1 3 that we are getting out of the FLECET-SEASET program, 'and 4 how we are going about looking at the data.
5 g I am going to'briefly go through the roles and l n ,
j 6: tasks 'of the program to give you an idea of the tasks ' stat- ,
p ,
o ' \
" 7 us and go into some of the analysis of the data that has
- 5 8
A been done and then conclude.
4 9
With regard to the goals of the program, I think
[.
C 10 g , the things that we want to highlight are that we are trying I
E j II to develop some of the areas that we can use to assess the f,12 best estimate code that you heard about yesterday.
13 g We are also trying to develop data that allows us E 14 g to assess the safety margin, particularly in the flow of
= ,
9 15 '
j blockage experiments such that the data will permit, a co-j 16 T
j ordinated re-appraisal, particularly of the Appendix K,
" 17 y where it applies to the steam cooling and flow blockage.
. 5 18 g A new obj ective that we have gotten into the pro-19 A gram is to take a look at post TMI situations where our pro-20 gram can provide information on the TMI type of transients. >
21 As Harold mentioned, we have generated a steam 22
- cooling heat transfer correlation which would be typical of ;
23 '
the boil off situation and we redirected the system of the i s_ test facility to take a look at natural circulation, reflux 25 cooling, the effects of noncondensors in the steam generators
' i i
ALDERSON REPORTING COMPANY. INC. l l
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I
- 1. We can break the FLECHT program into two main :
i l
2, areas of concentration. : i I
i 3 One is in the system during reflood, for both re-t 1 4 flood and for natural circulation and cooling and then rod ' '
s 5l bundle flow blockage.
a j 6 I am going to discuss this in detail today. 3y G i E
7j i looking at the system effects, there are three tests ' series -
j 8' which make up this particular work scope of the program. ' '
a ; l
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9l There are steam generators ' separate effects tests I l
o h 10 ;I which we have already mentioned. .In these tests, we have
= i l" II l taken and put it on a two phase downcomer position into the 12 2 ,
steam generator and the steam generator heat release.
13 We have completed these tests and their evaluation 4
reports are being prepared. I brought some papers which I 5 l g
15 l can give the committee that indicate the kind of informatiot.
16 .
I
$ that we got out of these tests and the model that we have j l
" 17 l
$ i developed with these tests, b I w 18 l g Again, the people developing these advanced codes l I 19 - ! l 4 ; can use this data and treat the steam generator as a com- l l 20 l !
ponent nou and develop or verify their particular steam ?,,cn-21 ,
! erator problem or reflood against this data. :
22 l The FLECHT-SEASET upper pler..:m tests, these are I
23 basically just counterflow tests. We have a little upper ;
plenum geometry difference going betseen our facility, tast 25 : ;
i facility, and the reactor, so that we will be running some j l
ALDERSON REPORTING COMPANY. INC. I
325 2 1, air-water flooding tests at EGG then. 1 i !
2j The system effects test facility, this is really 3 to take a look at the system behavior during reficod. The i
objective there is to provide a data base for a system re-4 l1 g 5 flood code assessment. I n l 3 6! As I mentioned, we have broadened the scope of f
- 7
$ 7 this part of the program to take a look at natural circula- .
s j 8 tion, two phase natural circulation and reflux cooling.
J 9 9 These are low pressure tests, however, so we can-
?
@ 10 not get the same pressure level that one uculd have during 3
I 11 the small break type transient.
3 g 12 The thing that a particular facility can add to D E 13 l the data of knowledge that is being generated in this area j 14 l is that we have got very good instruments, steam generators, E i t 15 ' and we can look at the steam generator response during these j 16 i different cooling modes.
- l
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17 We plan to look at injection of noncondensible h
= '
'2 18 gas also in these tests.
l g 19 l Again, the objective here is to provide data an-n 20 alysis which also can then be used to assess input codes.
i 21 l To reiterate the systems effects ' test status, f l
l 22 ' this task is complete. The evaluation report is almos !
23 '
ready to come out. The data report has been issued.
! EGG will be doing these air-water tests the first 25I part of '81. The system effects test facility is under
! l l ALDERSON REPORTING COP'oANY, INC. j
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I construction. We plan to be running natural circulation 2 tests the third part or quarter of ' 31.
3: DR. THEOFANOUS: Excuse me, but as you go along coul 4!. you tell us something about the chronology of all of these e 5i areas back here like when the thing started, not too mch, 9
6 3 , just roughly speaking when they uere made and when the re- .
E i E
7 sults are being edited?
8! When did the facility start for the systems ef-d l
3
. 9l fects test? I was under the impression that that was a very ha 10 old thing, something that has been going on and on.
E !
e IIj MR. HOCHREITER:.: No. De vou mean these tests?
a i 12 '
5 DR. THE0FANOUS: They systems effects tests, yes.
13 lz MR. HOCHREITER:: There were Phase 3 casts run in I4 :
$ l 1973 and 1974. The report was in 1975. Then the program 4
15 '
5 was terminated because there was a fear that there were some
= :
9 16 l z
scaling deficiencies. When we generated a new contract, we
" 17 '
3
= wanted to go back and rerun some of the system effects tests, 5 18
= in fact, run them in a modified system, in a system which j 19l' addressed those scaling concerns which were identified dur-20l ing the FLECET-SEASET Phase 3 program.
21 I lI DR. THE0FANCUS: That is what I am interested in.
22hi This kind of information, I don 't think gives myself a very 23 l clear picture.
24 As you are going along, it would be vary helpful l
if you will put into perspective what has been down new l
3 ALDERSON REPORTING COMPANY, INC.
327 J#y 1 versus what previous problems have been. l 1
(w- )
2i MR. HCCHREITER:
What we have done here is we I
3! have gone back. There was an AEC task force raport which 4
e::amined the FLECHT-SEASET Phase 3 facility and said, I e 5' 9
don 't know where Harold is who was the author of the report, 6'
3 basically that there are some problems with the facility in R i
$ 7 ~
terms of scaling relative to that.
s !
2 8' r.
-J Overall, it was not bad, but when we proposed 9
f.
that we continue that part of the program, we said, we will L
y 10 l address'those concerns that were brought up by the AEC task 2 11 g force. We have addressed that and the design of this facil-d 12 7- g ; icy and we have held two design review meetings, both with d
(x -) i 13 l '
other vendors and the NRC, to clean up all of these areas.
2 14 y ,
DR. THE0 FAN 0US: In the first part of the program, E 15 l j ~ i l did you produce also data, or was it stopped just before 16 r
$ l that?
H 17
@ 12. HOCHREITER: No. We produced that and we is-i
^
w 18 i
! sued two reports.
I 19 I A
DR. THEOFANOUS: Did you =eet the deadline also?
20 ,
MR. HOCHREITER: Yes. 1 21 ! )
h DR. THE0 FAN 0US: I am interested in knowing the 1 22 ll
- numbers of those reports because I did not see them, do ycu l 23 ;
know?
[~'N) i 24 <
1
\_, ' MR HCCHREITER: No. I can send them to you. In !
25 fact, I will send you the reports.
O !
3 ALDERSON REPORTING COMPANY, INC. j
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1 DR. THEOFANOUS: Now this in the construction phase.
2' this part of the program?
3' }!R. HCCHREITER: This is in the construction I
4 phase.
e 5 Again, we have broadened it to look at natural 8
6 3 circulation. With regard to the ficw bicckage grouping of .
E 5 7j tests, there are basically three tests that make up the as-5 i g 8 sessment for flow blockage,17 by 17 unblocked tests. These
'J
~. 9, are tests done in a 160 rod bundle.
m :
C l y" 10 ;' Again, we are looking for geometry effects, get-
=
l II l ting a day to day sign for evaluating flow blockage, pro-g 12 I viding data for reflood code verification, assessment. I
- 13 g will be showing you some of that today.
$ 14 l d i The 21 rod bundle test is a s=all scale test to E
e 15 l:
[ l examine the effects of bloc 3 age geometry and blockage dis-T 16
$ tribution.
H 17
_@ What we are trying to do is to try and test those E 18 g ; shapes which tend to be prototypical and present or repre-C 19 '
A sent different interesting configurations that they are go-20 ' ,
- ing to take.
21l h I brought with me a dami-section of this 21 red I
22 bundle with the sleeves in it. 'ihen we take a break, I can 23 show you what these things look like.
l 24 ,
j our goal here is to assess the effects of these 25 i different blockages, whether it be ceplanar dis tribution, i
1 ALDERSON REPORTING COMPANY, INC.
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- f- , 1I noncoplanar distribution, and different blockage shapes, and
's
- 2 to develop a method of analyzing the heat transfer data.
- 3; 4 hen we come dcun to this large blockage or block !
l 4 bundle test, this test would have both blockage and flow g 5 bypass.
9 i- 3 6! The objective here is to take this method with a
^
R l 7 .
\
$ method of calculating flow bypass and see if that method will
. 5 l g 8 help analyze and predict these tests.
d y 9 You have a model development test up here.
1 l
z We O
10 l h have a model assessment test down here (indicating).
=
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)
5
- I will be showing you some of the 21 rod bundle 2
f 12 data.
i / 5 \
S \- g 13 ,
- CHAI2 MAN PLESSETT: Will this be tied in with l d
3 14 E
e the slab core test facility data when and if it becomes a-t f5 .
vailable?
16
- y j MR. HCCHREITER
- We have been interfacing as close 17
- d"
=
! as we can with both the Japanese on this slab core facility,
\ -
- 5 18 ' l
= test facility, and with the Germans on the FE3A test, trying l n
. 19 j
l co get an overall program that is going to be assessing. I 20 l j j We hope to be able to tie this stuff together 21 1 l when we get it.
~
22 l l DR. THEOFANCUS: This development and assessment 23 '
,_ that you mentioned is that Westinghouse will be doing all of
( '
these things?
25 MR. HOCHREITER: Westinghcuse operating with the t
a ALDERSON REPORTING COMPANY. INC.
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I NRC, that is, this is a three party program.
2l DR. THEOFANCUS: But who is going to have the re-I 3l spo,nsibility of detailing all of the analysis?
4' Westinghouse.
MR. HCCHREITER:
j 5l The status of this particular test, the on block h6 a
?
bundle test is completed. The data analysis, the evaluation 7
j i report is being reviewed by EPRI.
n I -
D 81 q We have provided data to be used in a standard u 4 j 9l: problem.
$ 10 '
i
=
In fact configurations, we have completed, then, 2 11 j l two. We have two to go. We are analyzing data right now e
5 12 { to try to pick out what we think would be the worst sleeve 13 !
s to be tested in the 163 block bundle.
$ 14 '
s We have two effects here. We have heat transfer 5 15 I j ! of the blockage and then we have the flow bypass effect.
J 16 !
G This test will give a local heat transfer effect to us. We Fi 17 1
have to calculate it with that and we have to calculate the G 18 l 5 l bypass effect.
I 19 l N l We are losing COBRA code in trying to do that.
20 !
l We are trying to assess then how these will perform in this 21 !
l bundle because we want to test the one that is going to 22 l give what we think would be the poorest heat transfer.
23 That bundle would then have both blockage and by-24 ,
pass effects. 1 25 j DR. THEOFANOUS: Is that gravity fed?
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i 331 l
/'
Il -
MR. HOCHREITER: It would be both force flooding f 2!
and gravity feed tests.
3 DR. THEOFANCUS: 3ut your' tests have been com-4 <
i I
pleted, haven ' they?
g 5l ME. HOCHREITER: Five of the seven have been com-l fr 6l pleted.
n 7
- DR. THE0FANOUS
- Were they force feed?
n
'S 8 M
a MR.-HOCHREITER: .Let me then get to that.
= 9 g I want to show you know some of the unbiccked data
= \
b 10 y analysis that we have been doing and we think that this is E 11 g some of the data that could be used by the people who are 4
12 s $ presenting or were presenting the advanced models yesterday.
(
E 13 -
5 j MR. HOCHREITER: In our objecitves, we do want E 14 '
_y to provide data for this, becausc we think that we have got 2 15 y a test facility and a test design that can allow us to get 16 G ; additional information above and beyond what has been re-p 17 3 y ;
ported by the previous FLECT', heat transfer experiments which
, E_ 18 5 can be useful with these codes.
I 19 x
5 I will be emphasizing then this part of our ob-20 jectives. Again, I mention that we are going to look for or 21
. are looking for base line data, looking for both blockage
, 22 !
I and the effects of raw diameter pitch on heat transfer. We 23 1
do provide a single FL2CHT cor:21ation fer all of the 7LECHT '
24 !
v ) !
data.
25
) We are also, as Harold mentioned, providing a i
l ALDERSON REPORTING COMPANY, INC.
I i 332 i
1 1 steam, and developing, a steam coating heat transfer cor-2i 31ation, but I want to emphasiae this particular obj ective. l 3,
Quickly reviewing what the facility looks like, 4 i it is a full length instead of inside of a circular test e 5; '
housing.
R
] 6' To separate effects tests, we prescribe the flow .
R l
[ 7j condition boundary at the bottom, the pressure boundary con-
~ i l
u .
- 8f dicion at the top.
')
9i I
@ We can force flow through with a force flow sys-h 10 tem or we can attach a downcomer heavy gravity flow situa-5 11
@ ! tion.
M g 12 We have got Delta P cells, very sensitive Delta E !
13 l 5
=
P cells, every foot so we can get the void fraction and fe 14 l d is tribu tion. These are basically quasi steady state tests )
15
{= and so the Delta P cells work pretty well for void fractions.
16 i f
s Then we can separate out the liquid and measure
" 17 8
the steam flows so we can get a measure of the exit quality.
E l+
18 i
l We also have aspirating steam flow which is so l
19 ' l j distributed throughout the bundle. Using the measured heat I
l 20 '
flux, the measured conditions, and the steam temperatures,
'l (
il and knowing the flow rate through the system, we can back 22 '
j calculate down into the bundle to get the bundle average at 23 a given elevation, the fluid conditions, primarily the qual-24 3
,,y.
25 DR. THEOFA:ICUS: Are you really finding the quality?
ALDERSON REPORTING COMPANY, INC.
I l
333 :
1i
($ How are you going to know what is the actual quality in the
\' ') 2 l
bundle?
3 MR. HCCHREITER: 3ecause I have vapor measurements i I 4I inside the bundle. )
i 5
g H
DR. THE0FANCUS: What measurement is that?
, f6 n
MR. HOCEREITER: Steam probe temperature measure-
? 7
- ments, vapor temperature measurements. 1 E g M This is a cross-section of the bundle (indicating).
t l d .
d 9 j
These, of course, are all of the heater rods. These are E 10 E j the thimbles, which similate the control rod guides. [
E 11 ,
j These are the elevations where we had the steam 6 12 7s g probes (indicating). These are aspirating steam probes
( : 13 !
5 you suck through the probe. It has a double radiation shield E 14 s
around it and you measure the nonequilibrium or the vapor 9 15 j "
temperature in a disbursed two phase flow regime.
16
$ As a quench front approaches, these probes went .
H 17 ,
" 1 and we reached saturation, but for a icng time period during t
. E 18 i , '
5 l the transient, these measure the vapor, super heat, and tem- ,
t 19 !' !
A perature. ;
20 I can show you some of the data. This is at the 21 six foot elevation (indicating). I forgot to label that.
22 ,
l It has 40 PSI. This is the measured heat trans- )
23 .
fer coefficient based en the saturatica temperature, l
[
s 24 This is the CLAD temperature. We can see that se 25j d
are getting up to over 2,000 degrees. !
l ALDERSON REPORTING COMPANY. INC.
I
! 334 1
This is the measured vapor temperature. You can 2l t see that it is 1,600 degrees out, 3l It quenches b.efore the rod. This is the void 4i fraction that is measured with Delta P.
5 e
9 For these conditions which are the majority of
] 6 the conditions that ue are interested in, because we are .
Er i 7i interested in low flooding rates, PWR situation, the flow h,
i
- i 2
M e
8l regime that dominates here is disbursed highly nonequili-9 ,!
}". ; brium two phase flow, s 10 l j J MR. LIENHARD: E:tcuse me, but this work on equil-E !
y Il j ibrium gets me. Do you mean unsaturated?
e 12 E
. t MR. HOCHREITER: Unsaturated.
d 13 '
i ,
MR LIENHARD: It is equilibrium but it is un-E 14 h
i:
saturated?
F 15 E
MR. HCCFREITER: I am sorry, I have got satur-16 f
$ ated liquid droplets going throt.gh my test. Wait a second.
N 17 j ,
The liquid is at the saturation temperature. The vapor is 5 18 i g
l at 1,600 degrees F.
I 19 i 5 l MR. LIENHARD: The vapor is at equilibrium, un-20l ;
saturated and super heated?
21!
h MR. HCCHREITER: The vapor is super heated.
22] i These are the conditions for sO: inch of second 23 j 3 rate flooding test and again here you lose the acnequilibri-l 24 4 1
] um very quickly. The void fraction quickly drops to zero.
25 ,
When you are quenching the rod, ycu essentially 1 ALDERSON REPORTING COMPANY, INC.
i I 335 7N 1i bave a zero void fraction.
(v f 2!
The CLAD temperature really then turns arcund and l
3 the heat transfer is very high.
4 When we look at the motives for this situation, i
e 5: the flow regime that we see at the quench front or above 9 >
j 6 it, depending on the flood rate, it is an inverted annular R
$ 7l flow.
~
j 8- The liquid streams that go inbetween the rods e
I
~
9 l, that are eventually broken by the steam flow along the rod 's j
=
10 l surface are there. You will get to a disbursed flow regime h
=
l II 5 and it is usually at the very top end of a bundle.
d 12 E This is what the data looks like. We have been f-s 13 l concentrating on the low flooding data because that is really, E 14 i y from the PWR point of view, that is the area of interest.
F 15 j ;
In our data analysis philosophy, the approach we y have been taking is to try to reduce the data as such as F
16lI 17 y
you can without making a lot of assumptions so that you can
. G 18 l
=
r j
get down to the point where you can sort out the radiation 19 ;
t i j effects from the convector effects. I 20 l If you can do that, then you ccn take and devel-21lI op a first principal model like the models you heard yes-22 l tarday and compare the two. F.opefully, there uculd be an 23 independent comparison.
(T 24
(~-) ! We have tried to follow this philosophy as muc'2 as 25 we can. You can, judge for yourself the degree of success, i
i ALDERSON REPORTING COMPANY,INC.
336 1 DR. CATTON: Don 't you get sort of moving target 2l things like your receptivity changing with the test?
l 3 1 MR. HOCHREITER: We checked into those kinds of 4 things and by the time that we are doing this test that is e 5 already settled out.
O j 6 In fact, we have talked to GE, who has looked at R ,
- i 7j this quite a bit, and after about 10 cycles, it simply does
- j 8' not change.
a
$ 9I Af ter about 10 bundle cycles, the number on the 10
($ bundles does not change, so our analysis approach then is l
lII j to try and do a mass energy balance in the bundle using the g 12 ! measurements, using the data, and back calculate down into 13 l the bundle to get the nonequilibrium or real quality.
D 14 '
E ; To do that, we can use the vapor, measured vapor E I r
g 15 l te=perature model, heat floods and other conditions, and
~.
16 l j so on.
" 17 y , We have also done mass energy balances starting E 18 I
- ! at the bundle inlet and coming up to the quench front and it
- 19 -
I 3
then match these two.
20 l!
We can get the real quality distribution in the 21 '
bundle from these ki: 's of calculations. The assumption,.
!)
22 '
of course, is that it is one dimensional. It is not a sub-23 channel analysis. It is one dimensional.
24 DR. THE0FANGUS: Don 't you also have to show them 25l sc=ething about slip?
l ll l a ALDERSON REPORTING COMPANY. INC.
337 i l l C40 1! MR. HOCHREITER: Not in this calculation.
2i DR. CATTON: When you develop a correlation for l
3 things like the quench front velocity and so forth, how do 4j you correct for the fact that there are electrical heater 1
1 -
e 5 rods? 1 9 l j 6l MR. HOCHREITER: In our correlation, we do not.
E !
' 7
}
n DR. CATTON: But you have a quench front velocity
! 8 that would change if you adapt the method and if somehow J
}" 9! chat information is to be useful, we have got to convert i: 10 g that.
=
f MR. HCCHREITER: That is correct.
d 12 m E DR. CATTON: But you den 't do it then?
! 13 5 ; NR. HOCHREITER: liot in this program, because we
$ 14 y
don 't hcve that problem.
2 15 y CHAIRMAN PLESSETT: Where is that being done? I 16
$ was going to ask that somehow. Let me ask Harold that ques-y 17 5
tion.
. E 18 5 DR. CAITON: I missed something here.
I 19 ' '
A CHAIRMAN PLESSETT: When you get data on the e-20 lectric heat rod, how do you get this transfer? If it is l through the nuclear heater rod, can you reassure the naive 22 !'
questioner that you are taking care of this? Do you know 23 what the differences are?
( J 24 i V ! DR. SULLIVAN: It is basically--
25 !
CHAIRMAN PLESSETT: That relates to your same i
ALDERSON REPORTING COMPANY, INC.
i 338 i
l question.
2!
DR. CATTON: The quench front velocity?
3
, CEAIRMAN PLESSETT: Let us get a general generic 4
response and then you can get into the detail, if you want.
e 5 g DR. SULLIVAN: The process that we are using now n
3 6 '
g j is to use this program as a code assessment to provide a data .
E
- 7i base for code assessment.
n ,
a 8' M
The pin is actually modeled in the program as re-d t
9' g
c essing as it exists on an electrically b 4tra pin so that E 10 we get the conduction through there and mially we have E 11 y f gotten the heat flux going into the flow. -
12 j i
i Then we can tell the flow conditions and therefore E 13 5 we ought to be able to check and see if the heat transfer E 14 '
$ ; in the fluid is properly modeled.
5 15 l s ; When you go back and look at a nuclear pin, it is J 16l '
2 different. One of the things tha* you saw yesterday was that ,
p 17 j y ,
the conduction model is now going to be the FRAP code in a 5 18 l -
5 l large, rather, a TRAC code in the advanced codes so that we E. 19 :
a : will replace that with the model, the FRAP codel which will 20 !
not hold the nuclear pin, and calculate the heat flux out.
21 l l Then, even though the heat fluxes are different, 22 ' ,
causing the fluid conditions to be different, we should be able to calculate what a fuel pin wculd do.
1 We also have a program, the NRU ptogram, which thy 25 are doing FLECHI tests on nuclear pins, fual pins. That ALDERSON REPORTING COMPANY. INC.
l 339
/ 1
, would be the next step in the verification process.
V} 2 DR. EABIC: I was waiting for NRU. We actually 3i today do not have to wait for the linkage between FRAP and t
41 the codes that we have today.
g5 The code system codes can model the nuclear pin 1 d
6l, as well as the electrical heater pin.
7 .
"$. A number of our codes try to model the quench
. s
$ 8 d propagation and so on, dewetting from these first principais, 9
In our code assessment, we have done quite a few tests from C
' 10 s
= the old program identified by number, as well as from NRU.
lII We are checking our capability to reflood the cal-d 12 z
7-~ culations in nuclear as well as electrical.
( ,/ d 13 i ; >R. HOCHREITER: I might also point out that we E 14 !
_y have been trying to work closely with the NRU people e have ;
9 15 l
l companion tests between our tests, our FLECHT test and the
-' 16
$ NRU test. -
y 17 \
g s
) It is not easy. There are a lot of differences be-
. 18 '
5 tween the two test facilities, such as power, shape, and a 5 19 A i couple of other things, but we are trying to make those tests 20 !
l as comparable as possible so that we can compare the data on 21{ ~
( a one to one basis.
1 22l DR. SULLIVAN: I might add that the LCFT program 23 '
[ h also provides data with the noted exceptiens for the external 24 t (s-) k thermocouple that we brought up on several occasions.
25 t
CHAIRMAN PLESSET": Go ahead.
ALDERSON REPORTING COMPANY. INC.
340 I MR. HCCHREITER: This is the result of the calcula-2; tion of the local quality and what this uculd be 2t the 3l a::is to measurement point.
l 4 These are different elevations within the bundle, i
5
$ ten feet, nine three,.cight foot, seven and a half, and six n
3 6i o '
foot.
Eo
" y< .
l This is the quality that was calculated frem the v= -
8,;
9 bottom up, and at this elevation. This is not equilibrium u
9'
}; quality. This accounts for the vapor super heat that is oc-10 g curring in the bundle even though we have a two phase flou 2
11 l measure.
1
'd 12 g If we do an equilibrium quality for the same s!.tu-5 13 s ation, equilibrium quality calculation, the vapor tempera-E 14 l g ture is now assumed to be at saturation, although these
-P
- 15 l ,
curves just shif t up so that you can see by comparing the j
?
16 ! same elevation at the same time the pronounced effect of H 17 i the vaport super heating.
i G 18 g DR. ZUDANS: The gap question, does it mean that 19 t
$ the computer codes can model the gap or not model the gap 20 ! i 4
and that is how you resolve the problem? As far as for j 21 ! l surface correlation, does it matter what is behind the sur-22 face?
23 '
- 02. SULLI'/AN: The ansuer that Stan gave La a back-24 I up for one that I gave. There is a =odel in tha cenputer 25 ]
1 programs now, a simplified model of the gap :Onductanca.
!i ti ALDERSON REPORTING COMP ANY, INC.
1 I .341
' /"' 1 The plan is to make that more sophis ticated and
(
2 to make it a link between the FRAF code, uhich is a fuel !
3 red code, and that code has been subjected to a lot of ver-i 4 ification in the terms of gap conductance, both in terms of I
g 5l burn-off and also in terms of initial conditions on tha 0
- 6. fueh pressurized fuel versus unpressurized fuel.
, {
9 -
S 7 There has been a large effert to =ske sure that
. M 9 8:H M that code calculated the energy correctly and the transtant d
d I' j 9; gap conductance correctly.
o ,
P 10 i There are two parts to the answer. One is there
=
2 11 g is a simplified model in the computer programs now and as 4 12
,s z '
we continue developing programs, we will put more on that.
- 13 s ; DR. FABIC: The models for gap conductance, the E 14 !
_y codes do not allow for defor=ation during the transient and 9 15 j those models that cannot address that are, in fact, code and T 16
$ the appropriate inbetweens have already been transmitted to 17 '
F
$ code developments for these systems codes so they can also
. z 18 g address the dynamic changes.
t 19 i 5 l DR. ZlDANS: This program, the FLICHI-SEASET pro-20 l .
gram, it cannot give you any heat set in the defection of a 1
21 i l gap, right?
22 '
DR. SULLIVAN: That is right.
23 1
DR. ZUDANS: You are really not af ter that?
h) 24 l
\m / h DR. SULLIVAN: No. It is a very i=pertant par:
25 of the program thcugh becaus when you start looking at the r
i ALDERSON RE DORTING COMPANY,INC.
_ _ __ .. -_, _ _..... _~ _ ._ .. _ _.
i 342 1! neutral fuel reds, the instrumentation that you can get is 1
2! substantially reduced.
We are not able to tall in a lot of detail the j 3 j! i 4 fluid conditions, so we are depending on this to be the first j 5' part of the separate effects model development program, v
j 6 I think that it really plays a very key role in -
7, ,
=
E 7j: making sure that we can calculate the fluid condition in the '
! 8l heat transfer conditions and in the surface knowing the heat c
9! flux out of the rod and that problem is somewhat simplified 10 ' too because the conduction calculation is a lot simpler.
=
j II l It does not have a gap. It is solid conduction so l
- I 12 tha, 'r; can calculate that. That is put in the pin.
i
=
= 13
=
Westinghouse has gone through a lot of care to 3 14 '
E make sure that they understand exactly what those rods are.
u <
9 g
15 l ,
It is looking at a separate effects program that is actually j 16 !
i giving basic data, more basic data.
F 17 d DR ZUDANS: And Westinghouse is measuring rod 5 i a 18 i
= l surface temperatures?
E 19 l N ! DR. SULLIVAN: Yes.
20 '
c MR. HOCHREITER: . We =easure temperatures which 21 !
are inside of a heater rod cladding in an inverse conduction 22 calculation to get the surface temperature.
23 DR. CUDANS: That means that you 9111 come up 24 and set up correlations that should be correct fcr a given 25 '!
I t
! surf ace suf ficience. What happens after the surfaca is in s
I ALDERSON REPORTING COMPANY. INC.
1 l
343 I
I
/g 1' the business of other local effects?
\s / !
2l MR. HCCHREITIR: Our simulation actually starts 3 at the surface of the fluid.
l 4' CHAIRMAN PLESSETT: That is fine.
e 5 MR. HCCHREITER:: One of the areas that we have
'?
3 6' been expanding on in the FLECHI-SEASET program is trying E
E 7 to got more information on the droplets in the disbursed
- 2 8
$ j flow because the heat t : ;nsfer regime we are most interested d
- i 9;
[. l in particularly when we get into the flow blockage.
y
=
10 l! With the help of Dr. Y. Y. Sue and some of his fII excohorts at NASA-LEWIS, we have been able to use those re-2 12l, sources as part of our program to come up with better mov-3 5 l ing and taking techniques.
$ 14 '
y We have taken, I think, some pretty good high 7 15 j quality, high speed, movies, 2,500 frames per second movies,
.? 16 l l to get an idea of the droplet size and the droplet velocity.
p 17 g I can show you some of that data.
$ 18 i g l We need this information to be able to calculate I 19 !
4 j the split in the wall heat flux between the radiation and 20 l convection.
21 !
! As I go through some more of these slides, par-22 I ticularly when I compare them to seme of our predictive cal-23
[ )
culations, all of the uncertainty in that is in the droplets, 24
\~ / I from what we can see. That is where more work has got to 25 be done, i
, ALDERSON REPORTING COMPANY. INC,
I 344 i
I This just gives you an idea of some of the droplet j 2
data that we got for a particular time, two hundred to two 3! hundred and si:c seconds, at the si:<-foot elevation, uith a l i
4l quanch front appro:cimately at five feet. This would be like 5
3n a 40 mill drop.
6'
$ The drop distribution seems to fit reasonably well ,
h7 n
i along normally.
M 8 When we take and do a fore e balance calculation U ;
d 9' g-on the drops using a measure to calculate local steam vel-F 10 i ! ocities as we now know the quality, what we find is, using
!g 11 l I this type of a varied relationship, we tend to predict, 12 i j
'i j overpredict, the drop velocity.
- 13 1 '
E DR. THE0 FAN 0US : What is the steam velocity?
S 14 i
$ ! MR. HCCHREITER: I don 't know, about thirty to 5
s 15 l 16 ,
forty feet per'second, at about this position and this
$ ; time for this test (indicating).
n 17
$ We think there may be some work that has to be M i8 -
5 done when other people are using these advanced codes for 7x 19 '
a I interfacial drag.
i 20 We are trying to look at some of the work that 21 .
l has been done by ISHI to see if we can 't come up with a bet-22 ter drag relationship, but it is clear that we are not get- l 23 l ting that good agreement between cur measurements of drop I l si::a and the drop velocity versus what one uculd predict for l 25 l P l
l accelerating drops.
ALDERSON REPORTING COMPANY, INC.
I t
345 ^
l i
'r"
\
1 DR. CATTON: Isn 't that direction for the drops 2I sort of sitting out all by itself?
I 3; s2. HCCUREITER: A drop sitting out by itself.
1 1
4! DR. CATTON: A single drop? ,
- 5) MR. HCCHREITER: Yes. This drop calculation was 3 6 for an assumed drop size at the quenched front. j
, 3 n
t
= i It is actually for a range of drop sizes.
" 7 :
. m 3
" 8
' DR. CATTON: That curve is. '
d i d
g MR. HOCHREITER: Yes. i 0
9li .
r: 10 ' That is a straight looking j s CHAIRMAN PLESSETT:
- t E 11 ,
y formula, I want to say.
12 '
MR. HCCHREITER:. That is why I put down the ref-(' l ! l
( d E
13 !
i erence. <
$ 14 Pi l CHAIRMAN PLESSETT: Yes.
W !
t 15 i
$ l j 16 l ;
1 ., j d 17 i x e i
, z 18 l:
C I
x 19 ' ,
6 l ;
20 l l
21 !
I l d
22 ' )
i l 23 ' !
t 24 ;
25 i ALDERSON REPORTING COMPANY, INC.
346 \
l i
l l
1 CR. HIC:G2 ITER: Having inf or. nation on tha droplat 2! fiald f rom our .n0 Vies and having tha quality calcalacions, l
1 3; we can taka a look at trying to ' creak the reasurad ;all t e nt i
4, ficws into different components, . car t ic u lar . iv radiati:n of l
l c
n 5l drops, red -to-r:d radiation, radiation to vapor and t".e n ::ack
=?
~
$ 6 out of it, the convective neat trans f ar co -ef ficient . So WCat j
n a b 7 we put togethar is a radiation network. He have got six
, I j 8 I i surfaces. Ne have got tne cold rods, hot rods, symbols, the d l a
9! ,
vapors, tne drcps, and tne housing. And we :n c.v all of thesa O i g 10 ;
a te mce rat ur a s .
~ We kncw the ficw conditins and we have an idea
=
~
11 4 j of the droplet size. So we can go to this radiati n natwork B ,
g 12 l and calculata the heat flux split between radiation and kncwing T
- i a 13 ,. .w
=.
m ,
, ..<. a i ., i ,, . . ,<..
. . . a..
. _a _..
- g. ...e w .....
- m. .._4 5 14 '
G CR. THE CF A NGUS : How do vou knew the tamperature of w
L 9 15 '
y the drops.
=
2 16 B CR. HCCHREITER: Me assume sturation. I am sorrv.
s .
17 'i "d I should aave said that. That is an ass umption. However, for
=
6 x 18
- these low flooding ratas, since you are two phased at the s.
9 19 !
4 i
quenched front I think when the droos get further up, thev - -
20 !
are not going to get so cool.
I 21
.'.R . ~3
.. ".c .U.'.C U.c., - . .". o , '-
u* *" ...e.-a. w. .- a. . ' " . . . . ' . -....m...
22 temperature distributions that would have a very uch surfsca -
23 comparad to sne--
24 l .
sR.
.u. . uu..R _e . . e ,.
..s. ,. i,. .u- . .a .~.,e.
..e 25
, . . ~. .:..r - ,v6 A u t.m-sr u vG . .
,..s. a. C < . . . 2 G, .. ~. .; . . .a. .i4 , <... ,., y - --..
J..w=
ALDERSON REPORTING COMPANY. INC.
I
,2 347 !
.o-7 DR. ECCHREITER: The temperature of the radiation I
) -
L t 5
2 wo u Ld be the surface of the droplets and that would he at i l
3 satiration.
i 4j DR. THE CF A NCUS : 3ut wh:t you are missing--
.e 5 OR. MCCHREITER: The internal circulaticn..
7 I d
o 6l .
DR. THE OFA NCUS : That is right.
- i N i h 7i DR. MCCHREITER: He looked at that and decided it -
A
] 8 was uniaportant, b ut. I don't remember the details of it.
d d 9 CHAIRMAN PLESSETf: What was your point, Theo, I z'
E 10 , missed it?
z 1 ,
O .
g 11- DR. TEH OF A NCitS : My point is that they don't kncw 3
d 12 t he temperature, the unit temperature or the drop temperature.
f~~s g m .
g 13 Therefore, they do not mally have, if I know correctly, tha m i lb 14 l I
radiation component and this is the dif ference and & also E 15 i c annot be evaluated co rrectly.
a '
x y 16 DR . HCCKREITER : Well, another thing is when the W
- b. 17 i steam flow quenches, when the rods quench, ney quench particu-w x
w w 18 larly the steam probes particularly, they quench at the satura-
=
H I g 19 t ion temperature .
5 20 OR. THE CFANCUS : Cf course.
2I OR. HCCHREITER: They ars quenching from above wnich 22 w ould be the upper level, upper alevation and that is due no i
23 ' the droplets impacting on the tubes.
4 -
( ,/ 24l, OR. THE CF A NCUS : Yes, out they wi 1 approach saturt-25 tion very fast. :t foes not meet that the dr:pla: itself ALDERSON REPORTING COMPANY. INC.
4 i
348 I
is at saturation. In fact, I Know it would not be. There is I 1
a quastion on how far it is going to be from saturation. ,
2 DR. ECCHREITER: Nell, we will cneck :nat.
3, t
OR. AC CS TA : That is a true non-equ;11bri;m satura-4l m- 5
-1 4
c 6I OR. SCCHREITER: That would be an additional non-e ~
- 6 e quillerium situat ion.
- n. 7 3 CHAIRMAN PLESSETT: We will have to ask Theo abcut -
g 5
N 9 that later.
2
$ OR. HCCF.REITE R : S o using the radiation nett'ork, e 10 '
z_
gj knowing the total wall heat flux, we can calculate ne con-5 d 12 vective components.
z a e 13! DR. EUCA NS : Are you Todeling each droplet r what?
_d
- i E 14 ! CR. ECCHREITER: les, we have s u< surf aces in it.
w m
i l
'M
- 15
I Ne nave the cold rods wnich are the rod center of the bundle, w
.- 16 I am sorry, the cold rods which are the rods two ::ws arounc 3 i
-A :
r 17 the hous ing, hot rods which are the rods in tne center. N2 -
b^
w
=
$ 18 have got thimbles, which are a non-heating s;rface, and we
=
H E 19 have the housing wall itself, and we have the drops, and 5
n 20 we have the vapor.
21 l And we have measurements of everything with the I
i 22 e:<ception of the droplet temcerature which we assume to be l
23 ; at saturation..
24j ;a, ;ULASS: sut you do not model each droplac !
25 in this mcdel.
I
- ALDERSON REPORTING COMPANY. INC.
4 a
4 349
. . 16-3 1 DR. HCC3REITER: No. We use an efdective d=plet i 9 i size and we get the ef fective size from the movie data.
4
~
3.l CR. ZUCA Ns : Would you in the process compute tha j
- 4;I droplet temperature?
i
- s. 5 CR. MCCHREITER: Not if you assume it is a saturation ,
n f l,
. n '
- @ 6' "ecause the droolet has already evaporated. It is losing i
- t N ~
, d 7 mass.
4 . ;
l 8 Now, we have done calculations with this ne twork, i 0
[ 9 both using the droplet distribution and Laing the sauto: mcar drq z
a o
- g 10 l which we determine from the distribution, And then we rafine 3
z i i
11 ,l fron the cases we have looked, which is only a few, the
- 4
!- a l
! Y 12 l dif ference is small, in terms of how much the heat transfer i g = l l
\-- 13 !
)
is at saturation and hew much is at co nvec t ion .
b 4 N:w, looking at the convective forcs on the total b i, j
15 heat t r a ns f er --
}. l 4
x i I
i
. E
- lb CR. THE CFA NCUS : One more question, plaase, i w I l
t I
! N.
A x
II l DR. HCCHREITER: Just one, ves. -
I -
M 18
- _ DR. THECFA NCUS
- The view factors, hoe do you get i 4' N 19 4 % the view factors?
- n 4
DR. HCCHREITER: W e have used the maxi-code view 4
21} factors.
I 22 l l OR. THE CFA NCCS : This is acw :or a rod hundia? ,
i i 23 - 1
, DR. HCCHREITER: Yes.
\m, CR. TEZ CFA NCUS : Mcw about the view factors from l 25 droo. o ?ro o. and from droe. to :he :tructure?
i
! ALDCRSON REPORTING COMPANY. INC. l l
2
. - . . . . . . . . _ .. ., _ . _ . . .__.-mm.. . , , - _. --_--.-..-.,!
i 350 OR. HCCHREITER: We ass ume that it is from an 2
ccurately thin medium and I don't remember :ha datails. S 3
2ut I eink you assentially--
4 OR. TEE CFA NCL*S : S3 you ignore that in your view 1
o 5l factor from the drop to tne wall?
e N
l j 3l CR. CATTCN: You are ignoring scattering in the e t
= i
{ 7 steam ficw.in the sense that you only have a couple of drops.
M -
0 8 DR. HCCHREITER: Well, the void fraction that we N
d i d esti. ate f or these tests of these conditions is like 99 per A
9l o ,
- n. 10 cent vold.
E
=
2 11 CR. CATTCN: So you only need, you only '.cVe a few a
I e 12 d rops . That makes the radiation problem a lot simpler .
a I
=
3 g 13 What about if you back dcwn closer to the quench
=
E 14 front? i W
c
=
r 15 ca. HCCEREITER : Hell, then the radiaticn of the l w
x j 16 drops becomes more important, in fact, when we take a look ,
l 6 17 at the optically thin assumption that starts to fall apart I z '
=
{= 18 as you approach the quench front.
8 19 CR. CATTCN: As a matter of fact, I think it is 2
5 ,
20 ! several feet above the quench front.
2l OR.!CCHREITER: Not in our calculations.
22 2R. CATTCN: What flooding rate are jou looking at?
'3 CR. HCCHREITER: One inch a second. Or louer.
l CF. AIR MA N ?LES S ETT : Ua better kee p cving.
25 OR. CATTCN: If you can't see the drops, then you i
ALDERSON REPORTING COMP ANY. INC.
. .- = .. . .. ._ . -.
. .= .-
15-5 know you are okay.
I
[
t
\ CHAIR!1A'l PLZSSETT: Go ahead, Larry, you do not have s
2
'to answer every c )mment. I I CR. ECCMR2;T2R: Thank you, j What I have got here is the conductive heat flux o
5l divided bv the total heat flux which will give you the he:
9
- d
- 6i
- ,i rods and cold rods at dif ferent elevations versus tima and this !
D !
M
~
7' is at the s L<-f oot elevation, at the ten-foot elevation. ,
a '
8 8i
" 3asically what you can see is where the hot rods are six feet I d l -
d 9I !
g j early in the test about 60 per cent of the total hea flux !
o i h 10 ' ;
j l is radiation, radiation drops, the surfaces, and vaper. ;
E 11 i :
j As the quench front does approach, the portion of ;
l d 12 i
- $ ! the heat flux which is convection increases. Therefore, tha ;
3 ;
= 13 :t ;
E t portion of the heat flux decreases and as the quench fron !
z i x 14 I i y , does approach, a faction of the radiation heat transfer drops ;
r 15 ,
y does increase and it becomes more of a dominating term.
3 T 16 l i A l At the tan-foot elevation, thera is an even larger l*
- b. 17 i y fraction of the total heat flux which is radiation, quita j w I w 18 ; i 5 a bit of this is surface to surfaca radiacion, both to the j s
19 x I M thimbles and from the het rods and to the housing, because l 20 t
,- i these are the rods that see the housing.
l 21 l
)
. oW , know the Convactiv3 part of the total haa: i 22 !
flux, we can then calculation a convective nussait numbar ::y ;
23 ' l f
s ico. lv fividino. the convective heat fl=: 3" the sasur2d .;all l
+ ' m; i
. tamperatura minus the measured vapor tempera:ura >
25 ", i
? i l
i i
! ALDERSON REPORTING COMPANY,INC.
l
. . - , , , - - . . _ , , . , . . , n
1 l
l l
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! I am showl.g .vou the data, I don't thinh oculd c.ive fs~a a ta m,-,anaw_
..eu u ion :-
.4. ,
ecause .. a e n . m. .,.a.,. o-_3 .s.- :_
2i :. , o . . . .
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1 2 - . .
4+ *2
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. .'s s "">~ . . . -
e-....".
-m . -"-+
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l .
1 N
M,., 7{ a c.cr oache s , the data nussel: nucler incraases. ha situation N
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8, 4. a- s *_ _i .'. .' *5a. same a6 * = . , # = a *. , u . a *. *. *.". " ' a . ,
a_" .v d !
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- t. a..s e,-. -
. . ..'..=..ie...
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w i;- 10 i .t',4 T . C.A T*. C.P. N. .i..." ' . " . ' dead 3 a*.=. ^ #.
om-c.'.'--...~,, 4
, a
~
n 11 those nussait numbers look li<c you have the Nrong corr 31ation.
'J 12 a3 .. .%.^.C.'J.T2 . r' ". "..'. - ".' .".a *. . m y *, / e l l '. e .
z.
1 13 ' ,
-. . . w~.2 . . s . . . o- ..._4,.o . = ~ . - n. .e . . .va * ..1 .. . -
.m- ...e .:.., c'c. . ,.
a
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2 14 I i .., R . e. . r.C..., R. ., . .,. R
.,ai .: o- _4o - _ o . ... ;,e ... vu_ _. .
u t
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. : n"n' er o"CCc - . _- .an 'aoid '. a ck .
=
Ib 23. HCCHR2:ITFR : 'l o u have as ke d u r '.as : uestion.
Ef.
- n
.u. .
l a l71
.a ., t3 .
a
- m. .c._,v,- c g a. g'c .a .f 3 g ~2 3.:. A -
- w..
w 3 ,.. . f v~u, w,,
.. a. a 1 .
-.~..4..,.-
a ,
. a IO floor for nusselt numbe rs of over 1,000 and jou certainly u
8
' 19 C do not have laminar flow. ' lou have very tubular ilow, n
20 ,
.R . y .,C,.,. R ,. m..v, o
a .;,. , g o_ ,
. . . ., ,4,. , ,,, ., u, a _. , . o___ . . . .
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., ,d o s e .3. . ...,,.r a
a.a.
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I 23 Lo a u a, . _< .,. .:. u. .,.. . . . .g g. y. .t . . . , a .,., .-
u..s. 5.m.a. .. ,- , .~.,.:.
.v - o ,_, , ...a..
.,. 1 i
24 i -
as ou ad.d .la t = - ". o
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4.. ...e ALDERSON REPORTING COMPANY. INC.
i t
i 353 flow which could make the flor turbulent. This should certainly s increase the turbulence level in the flow wnich could be responsible in this higher nusselt number. That is our 3
.o l ,
suecosition.
e 5; We don't have quite all of the an:wers yet, but this l n I' N
i e
is where, what I am trying to show yca is where we are scing e 6 i
~
^
with the data and these, I think, are the things tha: .ceo ple .
7 S
- 8 who are developing the advanced analytical model should be n
- 9 looking tat.
i '
10 Now, we have got a dispersed ficw =cdel that was z
3 jj !
! developed by Sun Wong as a part cf his thesis at Carnegie 3 >
d 12 Tech. Basically the unique things about this particular model
/~'s i k E 13 is that it is fully for discersed ficw. It is where the
? !
= l
= 14l trend begins. It solves the enere.v. ec.uation for the vapor, x
w u ,
E
- 15 including the radiati on term.
w 2
- 16 , All radiation terms includ the evaporation of the 3
A !
g 17 i droplets so we have got all of the heat transfer mechanisms a i x ;
5 18 we think are responsible for the heat transfer in the vapor
=
9 C 19 energy equation. We evaluate the radiation terms using again 5
n 20 a radiation network and we also calculate the c0nvective neat 21 flux by taking the slope of the vapor gradient in the wall.
12 i .
This thesis has been published and anyone who is I
23 interested in it, we can certdnly send you a 00py of it.
24 i We do the calculations. You have to knew scre:ning
\s -) l 25 about drops though. S o I have two res ults : am showing you i ALDERSON REPORTING COMPANY, INC.
l l
l I i i 1 ac4 1
here comoared t3 the data, One for an input droplat at the 1
2i t
$""-,c ' --+,'-
-'- ---" "ma* '-i-~ -a - a* =---mi ' a l "' a --- ' --- i " " '-
- d = "*- a-9i l
\
l l
3l cne using this sauter mean crop walch we evaluaced from the l i
- 4) i movies, assuming that tne fr ps are 20 acceleraciag.
e-5; NOW, when I say terminal velocity, I mean tnat avery
- e. t N
3
. 6i droe. le t aas reached terminal velociev. .
Jroclee velocity can m
N 5 7 change with different elevations and this is the agreement N
8 w 8I with tne measured qualitv fata. - You can see we ara over d i 9 t. .cr e dic tinc. the quali v and :his will show up in terms of how
- z. !
. I h
- 10 l we =casure the va ecr temperatures. !
a '
= ! i i
G 11 l This is the measured vacor temceratura data and we I
's ;
a 12 !
predict the vapor temperatura data iust abcVe taa 4uench front ll s 13 l i
and we tend to ever credict it at the u.c.ee r e levations .
z 14 ;
s.
We do not have a good idea of the -ro.cer e dr c .
=
i r
a 15 mechanics, the proper intarf acial sheer between tne drops of '
- I J
16 the vacor and the proc.er dr 0 he at trans fer co-elficient.
. Ne !
s t
d 17 W i use conventional correlations f or those and tna is Nhat is -
=
4 1
z 18 .
res ponsible f or this underprediction here and this Over .cre-
- t. '
=
i 1
" i g
19 ' diction here.
n 20 Again, lock.ing at the vapor uality, we are undar >
i l
21 g i
w,, a;_
,----..; , n. .,,. a. . ".a e o- ,ual'".", - w. o- a .- a. .va- -- - :-
- =- d .i . .i ."e -i a . 2 -.".
22 1 .eaa* a..d u..da-
- d a..m '*", a
-- e .r e. d i c. *. i .+.c. . "$..
-- _3-a a. *. V. . a . . ~+'
, - --.- ~.-.' . a ,-
1 23 ! vapor amperatura again as a function o:. time, uscause we have i
1 24 i ave. , ,--------
.. me:-.3a ....ts. . ,ual.i." ,
n.i.". .# a a. '- , 8-a " da' i
-. --- : - a'. - ~- . '"e i !
25 i '
t
,! vapor temperature. ,.
i i
ALDERSON REPORTING COMPANY, INC. i
l
-355 N 1.,
I The bottom line is that I think we.have a lot of ,
i 2
data here that people can compare the codes against. Ne try 3! to analyze this data, again hopef ully with the minimum number i
i 4i i of assumptions, and these assumptions that we have r.ade hope -
1 e 5i f ully are programmed so tNe people can take Trac and 00hra h
j 6 Or Relap 5 and do the same thing. It will be vary interesting -
g '
$ 7 tc see the results.
a
^
i A 8l; DR. CATTCN: Properly modeled then in that regine, J~
l 9 it is really tough.
2, c
$ 10 ) DR. ECCHREITER:
z %2s.
=
$ Il j DR. CATTON: It is a scattering problem and everything 3 ;
i
( >
Y
~
I2 f \
alse. Is it really worth it to model it in a sys tems code?
a I 13 CR. ECCHREITER: If that uystens code is going to be 14 used to assess PWR performance duiing safety analysis, yes.
e 15
{
~
~-
ER. CATTON: Now, the Cobra Code did not have that I0 k
m sophisticated A Model as you are alluding to here?
17 I d"'
DR. HOCHREITER: That is correct.
m 6
m 18 DR. CATTON: Yet, it seemed to predict things very G
19 .
5 1 I
well.
20 I i
2R. HCCHREITER: I missed the C0 bra presentation 21.!
} yestarday.
22 <
DR. CATT ON: Not yesterday, I am referring to the 23 '
~
.orasentation at the Water 23act0r3 Safety Research .'3eting.
24 ,
! 02. MCCHREITER: All the Cobra pradicti0ns I hava j i
25 )lseen are of higher flooding rata tasts. Have they 100ked at ALDERSON REPORTING COMPANY. INC.
l l 356 I.
I lower flooding tacts?
2! OR. CATTOM: I am not sure.
I 1 3 All of the predictbna : have acen 3R. MCC:IR2ITOR :
4l arc at tho higher flooding .'ato test and it r 3q uir e s a lo a s I
5 sophis ticated model to do a good job there. I haca never aaen
$s g 6-i Cobra predictio ns trying to match our meaa cred vapor tempora-R .
R 7
.- tures or our measured or our calculated from data qualitics. .
n S 8' M I have talked with Cobra people and they hope to be at Westing-d c 9 7-houso nont m0 nth to got this.
4 10
@ l So, in conclucion, wo think tnat we have obtained
= t all of our objectivos and wo think wo have a goed data bania d 12 y for peoplo to use.
3 13 s l Now, I am going to gl ickly go througn acmc of tno
$ 14 l y j 21- rod bundla teot resultc i I can. Again, our objectivo on 9 15 l j '
the 21 rod bundle is to try and develop a model for flow 16
$ blockage, and do it in a small acale test and then qualify that l
d 17 i j l by a largar scale test.
M 18 I g l When we look at flow blockage, haalcally No have 19 k : competing hoat transfor effacts. As I motionod beforo, radia-20 !
tion io significant and wo do have two-phase ficw contrary 21 !
h to Appendin X oven at very low flooding ratos. And looking at 22 I t ha compe ting heat transfar affects, if we nava tha .Sy-pass 23 offact which abould give you acat transfar penalty, Sut the 24 1o t
+
droclata that are atomizad wita the flow can result in heat 25 ;
trann f ar improvement .
l ALDERSON REPORTING COMPANY. INC.
l 357 1! Mhat we have to do is construct an experimental and 2' analysis program that is going to separate out these two affacts 3 s o we know when one counteracts the other how important is l
4l droplet broakup and mixing compared to flow by-pass and we try i
y n-5l to factr that into the design of these experiments.
i n
2 6l To do that, we have had a lot of help. We have been O
- E 7 in contact, of course, with the oak Ridge Program to help give a
2-4
'd 8l us information on bloackage and shapes. We have used some j
9
~. I outside consultants. We havg.got input from the other vendors.
n 10 g We have Gotters Pickels temer involved, Ralph Meyers, and Dale 2 11 g
Powers from the NRR and they are providing input to us. Of 0 12 g course, we have had the analysis people. We are going to have 3
13 i , to look at this data and our analysis to make a judge.ent as 3 14 f
to whether we have answered the question in Appendi:: K.
9 j 15 l We have got these guys as involved as we can possibly 16 !
$ i got them. I have mentioned that we are trying to integrato
- i
- b. 17 y ; our program with the Kolsruhe 7eba program to try to get a way E 18 ,
= of complementing the Flux program and the Febs Program. The C
- 19 .
4 i Feba Program is primarily concerned with code planner blockage.
20 l We ara mainly concarned with,non-co-planar blockage .:acause 21 that is what we see in the experiments.
22 l -
20 have used other inf ormation and all of this 23 *
, stuff has bean mismashed tagather to coca up with our stracagy-1 24
'- I And as I indicats, our stratag-; is to come up *.i th taa rod bundl-25 to screan dif f erent shapes, to 2::2mine co-planar and non-co-ALDERSON REPORTING COMPANY. INC.
-. .. -- - - - -. -- -~ - - . . - -. - .. - - - , , - . . .
1 i
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3 -,4
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N 7
4, cur data is because in many cases , the bicckage effect is small.
N 8 8' u ,aa,n. :..... m.u,e au ..a N r w a .nm.m u
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3 Z i Cur c. .2]ective here is to deve.co a ,;._ c.cac.a anal./s is .
n
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d 12 y will have ficw by-pass and we do that test usi..g ths -. cst
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ALDERSON REPORTING COMP A NY, INC.
1l I
I w e.
, will allow us to distribute the blockage between a a. rid s.ean, n- 1!
(y) l all rods blocked non-co-planar long, non-concentric.
2 Scw, ;e are making a judgment on this data what 3
this shace should be, short sleeve Or long sleave ?.nd then we 4,
i eq .4.1 1 ,S g 4..w6 m 6. s _$ a -mi.re- 4 .q u g s op. .i ea % - -. .. ..
- .1 a 43 ,. ..w.e 4--*
-aw --..A?
.i.. 3 e 5.
n i i built. .
e e
j DR. CATTCN: You are using the Cabra to calculate n,,, 7 E the hv-cass? ' '
2 8 n
- d. .'.R
. . .'J. CC.'-IRE '. ". '. . .- '.' a- ."a .
z.
,e
- DR. CATTCN: And the is a two-pnase ficw problem?
6 10 +
z E
z DR. ECCHREIT2R: And I am doing a single phase.
11 3
c-It is earv
- that way.
12 C
t-E a These are what the sleeves look like. This is the -
= 13 m ;
3
- 14 long, non-concentric sleeve and I have got these On the test j w
E=
5 I section over here. This recrasents basically what is Observed
.r 15 ' -
w z
16 at Oak Ridce and at Karlsruhe for uceer : nase bursts.
This is n
2 g 37 a low temperature,high pressure burst. This is the short, w
f concentric sleeve. This is more tveical of a hirn temcerature,
. w 18 -- - -
=
l h 19 , low pressure data phase burst. This is, most cf the reactor 1 5 1 M i 20 vendors would calculate bursting at this range and would have t
21 ! '
this shape.
i 22 I i I. ant to show you some data comparing the different i
i 23 ' blockages and a flooding rate of less than ons _..ch a second 24 i so it is less than the magic cne inch a second :2 3.ppend:.:: K.
V l 25 ' The initial temperature of 1,500 fegrees, savon :ll:wa::s a i::t i,
A i
i ALDERSON REPORTING COMPANY, INC.
i l
360 l
I 40 psi.
These are the co-planar tests ?.nd we are looking at l the centar rod. This is taa ':lockags zona and again it is 3l 1
)
i co-clanar so it is vary short. These are the grif locati:ns.
4r 5
i This test is f or all rods blocked co-olanar.
This is 3:r nine e,
n i 3 rods bloched and this is the referance test and una; you are e
e 6:
y 7!
generally observing is downstream of the blockage, the more
- 1
~
blockage you have, the better it is. There is just no flow U
n 8l hv .cass. So the blockage acts as a crid, breaks up the drops, 3_ 9, ,
a 10 ' i mixes up tua fluid and gives vou a good beat transfar.
and
- c. ,
i a_
jj that is what we will get out of the 21-rod bundle.
E ;
e 12 ; Now , the question is hcw that pe rf ormanca , ce ing z
- i 3
= 13 '! a larger bundle, we have flow bv-pass and that is why we have
- - i
_3 14 !
i a laracr bundle test planned.
w' 1
6 5_ 15 ! DR. CATTON: Do you maka a Delta P across the block-E
~
i l
16 ; age?
3 A !
OR. HOCHREITER: Tes, we have. '.!e aave run hydraulic d 17 w
x
$ 18 tests and we took the K from the blockage. .
" 19 , CR. CATTON: That seems to me tha t that is tne 20 !t answer.
i I
DR. MCCHRZ:TER: As long as you are willing to use 21l ,
i that kind of an approach where it is co-planar, I ch ah /cu can 22lt 23 I come up with a pretty straightf acuard mofel. It is ic.en it is 24 ! non-co-planar it gets kind of squirrally.
l l
b DR. CATTON: **Du Nould 3till haV9 th3 LaCa Calta 2 l
l l
1 t
! ALDERSON REPORTING COMPANY. INC.
361
.I across the blockage and cculd calculate the flow.
l
\
2 D2. HCCHREITOR: For a acn-co-planar case, Uc do not 3~ We the L0ca Delta P, but we will have a Celta ? across the I
4 blockad rena with a non-co-planar distribution. The fl:w e 5 can snaka in-between the reds. .
R .
o 6! OR. CATTCN: This is ::till- coing to ha erottv
- . much R
n 7 uniform pressure.across the channel. If it is, then you cal- -
M j 8 culate for aach blockage where it is fLewing.
d d 9 DR. HCCHRSIT23: I know, but there is still a lot of 3[ c
@ 10 cr:ss flow. The pressure 4 s probably fairly uniform.
z
=
j 11 OR. CA'I'roN: It is going to be necessary to adjus t 5
g 12 the ficw. So if you have a Delta ? across that blockage, you D\ 5 V y
=
13 can =mputa the ficw to that local blockage.
14 02. MCCHREIT22: Or use Cobra.
e '
2 15 DR. C ATTON: Sut you would put those K's or so forth w
m j 16 in the cobra, wouldn' t you?
A
~
I7 DR. HCCHREIT23: I do n:t want to get into a discussion m
- $ 18 - -
_ or Coora now.
C b
g I9 i CHAIRMAN POSSETT: Please proceed.
n 20
.CR. :cCHREIT22 : You can see that the all 310.:k case 2I gives you a 10wer tamperatura rise and in this case, it gies 22 a higher heat transfer.
23 Looki:q a little bic f urther dcwnstream, this is a i bear fluid thermal coupler that is sticking into the sub-25 channel and I have get some over here to show you.
- ALDERSON REPORTING COMPANY, INC.
i l
i 362 l
I Now, the scale here admittedly is pretty small. But 2
generally what you see downstream is less superheating for the 3
blocked case compared to the unblocked case. So the drops are i
4' more actively contributing to the heat transfer. and i: super-e 5 g I heats the steam, n ,
e :
n 6 lI i OR. CATION: It mi::as i;?
n* 7'
.,, DR. HCCHR2 ITER: I t mi ce s it.
U '
s 8 i
At aight feet, this effect diminishes. Thare is d !
d g 9l clearly, from what we can see in the data, an L over D effect.
E 10 i E l It is just like you see downstream of the grid. And as you get 5 11 F
g to eight feet, that effect diminishes, but you still see heat d 12 l z i tr a ns r.er improvement and you can see that right here.
= l 3 13 ,
o a For the case whera we have nine r:ds biccked, tnare E 14 a
e i is barsly any difference.
-2 15 s In looking at the steam temperature again at eight f 16 k
A feet, No. 3, which is the all blockage, still shcws some de-F a 17 y i superheating. There is a little bit of desuperheating for the
$ 18 5
nine rods blocked case, but the effect diminishes as you get 19 k ! further and further away. So much for the co-planar.
I 20 i ,
For the non-co-planar, this can be very acay to 3x-21 plain. Bas ically, the sleeves ara adjusted to match a calculated 22
! temperatura profile. The burst location is in tha sleeves. 53 23 ,
there is a peak, b loc.Vage location and I believe I .:ava i:
24 ,
i covered and it is right in here.
25 That I am going to show you is some fata d:wnstream ALDERSON REPORTING COMPANY,!NC.
363 I of one of these sleeves.
!f-^)
2 Now, you get two effects. ' lou get the effect of the 3 sleeve itself as it affects these measuring scints downstream.
l 4l Sut you also can see, and it may not be clear in the things I I
g 5i show vou,.but there is other data that shows it. There is a g l -
+
2 0 cross-flow ef fect from sleeve to sleeve. This is for the
- R R
' 7 This is for the long non-concentric shat-concentric sleeves.
s 8 8 a sleeves and this is just an artist conception.
J d 9 g Now, we will be comparing this same anial position c"
10 j between these two bundles. I should mention that in the short,
=
2 11
< concentric non-co-planar distribution that the ma::imum planar a
d 12 5 blockage is only about 12 or 15 per cent because they are short
(N g (s -
13 sieves and they are distributed.
5 E 14
- For the long, non-concentric s leeve, the manimum
=
7 15 j co-planar blockage is about 26 per cent because the sleeves 16 '
$ j have got tails on them and those tails add up in terms of i
P' 17 l d i flow area bicekage.
- I
- E 18 '
g so looking at this position with the blocked zone, I 19 1' A No. 3 is a long sleeve and No. 2 is a short slaeve and No. 1 is 20 a reference chasing all blockage. And again, No. 2 and No. 3 21 are below No. 1. So you see " eat transfer improvement in the 22 ,
j blocked zone in the 21-rod bundle where for either the short, non-concentric sleeve and the long, and that shows up in these
[~'h 24 I
(,,) ! figures.
25 l
Now, I am going to skip the next two'.
I
! ALDERSON REPORTING COMPANY,INC.
I i
364 l 1
i At 73 inches, again wa have a stam probe and this !
2- is sticking down into the subchanned and again icu sae da- ,'
I 3 'i sucerheatin . Particularl" for the non-concentric slaave, thera I
4' i isa d e s up e . .". ' a ' _i ..~3 ^ # _# _' c '. . S - "; ~.'. 2_ .=. ~ :3 * . .i n '" . ..i .". _ .m. ~; .
o 5' ,
.3..... v y..a .. . .w. 4.o, 3 u. 3. ... , , u .' .-.-.v a. .o l. _- - +. M
.., ,,. r 3. u , ..
g . .
o l
- there is on t.'.e siseve, re ,
D re /
- ~
a.q . w ..e.'C'.3..R#a- *w'".1. *25.4 a~ _' a '. ".e
. v .' o. v .. +. a ..". .' a. . a '. u .- a .
to '
8 8l
,j In this particular graph, it in the vapor tanceratura.
- 9l The othar gr:phs are the tamparaturas on the rods de'.instraam of g
d 10 l I
the sleaves. Thev. also have caernal cou-lars e an the s'.neves
=
w 11 i 3 -
i thems e lve s . ~ '; ave not shown you any of tnat data.
J E
12 I
=
- ~ ,
-vu. .a . .
,u . ,..v , - , , , &. . . i .
.. ...i, a e. u-_ ., o .e ms .s. o .,.. , _4 . . _4 +. , r _
3 3
13
~,
ast as to ehat nappens whara t h o s e '.: '. a c ka ga s o c c ur .'
E y 14 I .
5.,,
i i
9
- s. . . .:. C... . &
m-n.x. . . " % .-, ...
+ . . , . , 3 a_ 3_ _2 1 ., , . , . 3 4 3. , 3g i
. - ,3. a ,
=
r
. I W l 3 .,. 3 _1 .3 , ,u s u ' .- ..* f 3 -*3 ^ t 'O d'. C i%. '*. ' . . ' . ' . ' ' . " ~. ' . ' . " ' . ~ ^ i . . ,; _' a'" "'".",
= . . .. , . ;s_ .s , ,
- ,, 16 ,
w !, . ,s.. s _4 ..,.-_, , a +. , a,, a. -..a. c + o .. . , -
.. 4.. ..a _ , s , i. m. . .,
%. . . ,_.,,.,.,..,o .e ,,
t{ 17 5
I stainlass steel and the.v are not Circled well. So Wnat W are a 1 '
i 2 I interested in is the heat transfer offect those slaaves cause s
19 ' .
b on the ficu going past downs t r a am. '1a ara not that atarastad 20 t ' "
.>". .. m.e .
3 . "..".a 1.. c '_ a . . y e " a '. u ..
- 3 .# d ' r. . _- ... ...3 - s '_ a a. v e. . . _ _ _ ..
21 ' i
.. 3... , a-., , . , _4 .. -, .,-
- s .n o t n- " *. . ~- N. . , ~.-*.."..a."..";-..A -i".'. . .-
22 l
._ . ..-..n a,,.a_ .m.,,
,o-_e.
23 w........ .
2a ;... . . ... ,.. . ., ...
. , u,a 3 _, :n . .
24 i
.... .. ~s....-.....
~ , . - . - -
. ._.o . , , _
,n... , s.
25
- n. y. _4 ,~ .u..o s-
.- _4
. . . ..o
- .. . . . ....a .,_._m. ,. _
_. c . ;,
t I'
- ALDERSON REPORTING COMPANY. INC.
1 i
.. _ - _ . .- _ -. - ..~
l i i
i I
i %
a6a-
- I the diff arance is much smaller so '>cu have an _. Over D ef fect
)
a '73 0 f 0r the non-Conc 3n".ric hlOch3.
3 o. .u ..., .,a-- 4.,
a.3 . ,..S u ~ a . 'b$ .'. *. .' . . :- 3 -- -:' '.a....'-"- w
%..... .. 4. s . .
4 ,. , a a_..
.,,,...,,3,.,_
_ . , _ . . . .o . ., ..re n "~- .*.c'.*."._ . _d a~ '_ 4_- , =. _ . 1. ;~ ' _i .*. , .'.,._'o- _8a-i e
- 5' 2ecaus a you ba ve more .01 . ,0caa. a.
9 e
$ 0> Since thera. is no flow by-pass allowed at the 21-rod l
- i n
b 7 bundle, all of the flow has got to go through the blocked =0ne "
n
- 8 M to help break up the droplata and that give you more dasuper-d
- ! 9 .
g .n e a t in g .
e l': 10 i tiow, how a':e we going to lock at this faca? Of E l
=
~
11 '! t,nd the -approach
$s c oursa, we are going to lock verY carefully.
i c' 12
.5 that we are taking is to use this first ac.croach, a modal that .
3 s -
13 m
a ,
'ias
. y- '.'. 'u " --z a '. .%. a.. - '",r
- u.a ' .'
.: a..' C~ a m a- -i"
- ...'- - - . . ' . .'/ .$. a a-E 14 d ago. The '.iay the model handlad the haat transf ar .nachanisms k
c 15 W
m was assentially makinc the model applicative. - 70u have 16
)T a 010chaga effect,an enchancement effect caused by the blockage b' 17 w
and then rou have a heat transfer flow by-pass af f ect which is
. W 18 this term hers.
19 2
a Mcd , we have constructad our e::perimen s. Thera 20 is really sor.a nepotism in this.
21 C.wh' . 't' 'uM' 2 .4.
- ^-
T ' 0 0 . '. .'
. "a s * *'w'.-*.
.v g' '.'. a' '. ".-*..~.~'.'.i..~;
..a "w..at.
22 C3. HCCG2IT23: Ne have constructed our haat t:a nsfer 23
! 3::ceriments so that we can separata at these t'.lc affccts.
24 '
( Uhen we run the 21-rod hundia completaly ':'.: chad, -
le min-
- 25 '
1.ni:3 this tarm. Thors is still some subchannel to subchannal l
l l ALDERSON REPORTING COMPANY. INC.
l s
a6C 1, c'..t .=..=..= _r ,. C _o n- a..A- , , = _ 'n a </_a +o
. . c "w . . ".
-s- " .". a"w a..A c.a+m, aw un
~ m "w I
2; .... . _ ..a w v ,, m 4 .._ 4 .
,d _a ". . . .' '-.; -
- _e , ~ ' ' * ..
r- Y. - ' nh _ a . . - .~ r.*- .
i 3I Uhan WG go to a larger, block bundle tast, we ave 4i +-
es c a _' c uu n ' a"u- ,_ ~ .u. _t o e._' a _v m - ./ ,_ _- _ a _t . . -: . .u. _: o- . .u.a t <.v e - m _= _- _ m ..n 5 'o ' _ _e .- n..,.A_ _' _, .,s~ ~.o see .t= . m. c . , . . ' . v e o _,u___- _n o_ A- :
e w..._t- _ ...m_
v o
, 6, 12-:o_- '~-u..e .' .e ..,. .
n !
$ 7' so that is the approach.
=
> It is a ver.v sia-listic e n
- j i
8l i model. Dr. Ouffy has already fon2 some calculations using J '
d 9 z_. !,
our 21-rod bundle data and the feed bundle data and he has y 10 i z !
got some fairly good results that would indicata that par-
=
11 i
haps a simpler expression here may do the job. 2ut this 4 ..
a 12 >i woult ce amo_r_, cal. .
=_ \-
a ,
- 13
-=
..~.v,
- .. . jn uu. g m.
,__ , o- s . q...,... -.., , , -
_4o. . 3.> s. _, 3 u..e __
e.a 4 ,,o z
14 '
?
- 1 i
dispersed first model that I described to you and see if ee
=
r 15 '
2-can't coma up with mechanistic reasons why this is shat it 16
's A l is. Wh'v does two-chase effect flow offset the by-pass effect
~
g 17 a of the flow'
=.
w l o. r 1 In a.c.cendix K, this thing is one and all we have
" \
19 3
n ; is a .cenalty. I think to convince the . cec.ola uno want Oc 20 l '
i 1
changa this rule to make this numhar c.reater than Ona, we h ave 21 l j got to have a machanistic arguments.
22 ,
1 So concludina, we think that we have triad to 23
+ , . , _- ,
c ow _..,-+2.,
ww. '. .. . ,- a y .. 3.,. + a + . .g -sw, o u. , . .--. ._ -., -. . . , : - , . o, . . .
. %_. . ,m_ s o, 24 !
t
.. .a ,o ,.l - . a . .c:. _4y. .-_
o- - , c _, .,.o :
, o . . c .,. _ . . .n.a. m_
_e c.,
u .',. , o- m _e . . ,, ..
25 outstanding 'icansing concern since the cora cooling '.aarings ALDERSON REPORTING COMPANY, INC.
I 367 tN 1 in 1972 He think we have a program that can adfrasc that (s/ )
y and hopefully provide the data that can be used to reassecs 3
! that particular part of the program.
1 4i 1
i
.12 have made Our .croc. ram. Ne have sponscr2d the e
- 5l ,
9 : Three-Mile Island. He draw the system eff2 cts and we are
- i e 6 ,-
e g j going to be looking at natural circulation, reflect conden s- 7. I
. ; l sation, twc-phase natural circulation, and the steam gener-3 8!
n
. ator behavior with and without non-condensablo gases.
d 9 y Ue beliave that the program is generating and h 10l
_5 ! associated analvsis .
which can be used by our brothers in 2
< 11 l 3 l coda development and verification to test their T.cde ls 0 12 '
/~'N F < h against it and I would very much itke them to do that so s_- /
\ : 13 l a
we can get faedback from them.
$ 14 w
$ OR. CATION: I just have one comment and tnis is, r
w
= if you wara going to try to get af ter Appendi:: X, you are 3
16 i M
i going to have to do scmething better than single fac3 C0 bra s 17 w
g to tie this thing together.
z 18 CR. HCCHREIT2R: ac soon as there is something E
x 19 l i 1
" I better than single f ace Cobra, we will use it.
s R. CATTCU: We c. ave neard from your safety pacpla t, a . . w- U u.
. v. .u. .s . ..f. . r.
22
& 4- &
4 **y 5,4 7 s . -. wm.J.7. .5 m..T.. m.\ . m. .L =
S
= J .m. w 4 .s e4 -.
. ..wn / -s-23 I
l
/N r 24 dispersa ficw.
i ;
N~ '-
.'.,.s. C.;". *. csN. -. *"a
. . . .O i,v v .'. s. .v .
I w. ,
yw.m ?..*s.e 14 qa.] *)
. .r S. .C *?
wa m m. .. mk.
A. 3.m.A j .msg e *e 3. ; .
l ALDERSON REPORTING COMPANY. INC.
i l
363 l
I. DR. Z UOM S : May I ask One, brief question? ;
l 1
2 C.:... , . ,.
.w. . . ,1 .3 L. .,.S o a-. . . .. .... ., s .
I I
t 3 ;3, ;g33;3 . 1 hat will happen, hcw ara fou ;cing 4
to describe the situation in :nis blockad none if bnis in-I g 5 i :ormation g ves the result beyond thit point?
M
$ CR. SCCHR2 ITER: ".le will be 90tting haat transfer rT
?.
3 7l results in the blockage zone. Some of the data I :hcwed you e- *
- I A
J 8l l was in the blockage ::one.
d 9!
.g DR. ZUDANS: I see.
o l ,
10 i j OR. CATTON: The problem is tying it back together.
=.
A 3e ,l
< l When vou have the blockage in the middle of the core, vou a !
12 !
2 have to know what the flow through the blockage is in order
- i t
- 13
= ,. se.a ,- u-
.a . a,u, .-.,.u,, , g -u
-- .3 . f a-
. .s .. ..o ~~. . .u. , .. o ..--- u .n. v e ...-n g .
2 ,
$ 14 !
i'!
h:
I l
CHAIRMAN PLESSETT: It is a very good program.
9 15 !
l Certainly we are learing a lot. It is not finished, but that l
T 16 3 is what we are tryine to s av .
.o i Larr"2 does nct s air .
d 17 g was. 2:either did Dr. Sulli"an. I think tha'. it si ce
>o 18 .
- encouraged to co - on.
8
- 19 <!
j t is gettinc a very interesting and usef ul data.
l 20
- 02. S ULLI'/AN: Can .;e make some concluding 21 remarks?
22l ,- - =-
,~.,
. , .-. , ru7 3 .c .e .c. . . .,e,,,
. - . u .s.ava y ,- .-.. .. - - ur 23 minutes.
24 a
., .s . : . .- - - .v u u s 7n,s7
.. .v w. o u .' .4 ,' us 1.4.~h-- *- -='"e-*s
- - - - - - - - - "a-25 it is the ::rporate program between :ne '; RC, :7R:, and 11esting-1 I
i ALDERSON REPORTING COMPANY,INC.
I 369
'I . house that will becona. And I would just briefly go through I
> l 2i these, the application of the results, the appropriata status. l't I
3 There is a financial difficulty with the program and I would '
. l t
4l like to addrass that . and mairbe ~
get scme comments from you : >
t
. i 2 ' l' about that and our futura clans. * !!
n ,
a g 6 Locking at the flow blockage work, it was to l
. g ,
a 7 i b address the Appendix x flow blockaga model and there are two '
. m i 8 A- parts of it. One part of it has been completed and that was d
- 9 z
doing reflood axperiments with an unblocked bundla and tnat !
O
- 10
$r' has been completed. We are now looking at the 21-: d bundle
'5 11 j and we think it addrasses the Appendix x problam, also the code d 12 i E.
I develocmant .7::blem and Rolao.
c 13 i 3_ !
Tha syst:=s ef fect .ecrtion of the ::: gram, the E 14 l d staam generator and heat transfer data has been producad.
=
_F 15 w And new, the systems part of it is both the reficcd and the m
16 h ,
natural circulation as Larry indicated, i
p 17 ! !
y Locking at the 21- cd block bundle past, there nava
- w 18 5 been five of thas e bundles completed, the tests on them i s
- 19
= i a and thera total Of seven plants . The estimated completion 20 ,
! date is June of 1981 and we are projecting a cost overrun 21 On that particular test.
22 !
i The 131 rod bundia as Larry indicated to select
, 23 l l ,_ the worst geometry from tha 21-r:d bundle program anf tnat program is in progress, the construction of that, and :he 25 \
! tasts ara astimated to be comolata in Octcher of 1962.
I I ALDERSON REPORTING COMPANY. INC.
i i
370 l I, !
I ' Tha last portion of the program is the raflood !
i 2> portion in the natural circulation and the const ucti:n of the 31 e a c i .'. ., _i ' v .i s is . y.- .19.-a S s an A '.".a 2 " L' .,, a -' d
. w- a smo. .-
' - .^ . .'.a.- o.-
I 4! t.%.a ,. .a .. 31 -
- .,,1.3
.v. at .4 ,,n, _4 o
,e 3
.,. , . , , ,. _.. . . , . ,. , - ' 2 . a . . 6. " .'-'. =.
. . . a- < r .a. " ' m c 5 ficed is May of '32. .
9 g 6 Mcw, it is important that we keep in .-'.ind that there , .
v >
'l 5 are three . carts of the .crocram. Thera is a current, .Oroject- i e ,
i 8 '
s i ed cos t over. un of about 63 0-K.
J
- I
- 9i g ; CHAI 01Mi PLESSETT: Harold, is this the total over-
.t g 10 l run?
= '
.z 11
$ DR . S ULLIVA N: It is the t0tal, projected Overrun u 12 i E
as of about one month aco. -
- i-
= 13 1 m
~, r. 3.,7 w..a .u . e.r av e .. .
a mv .w. _: s d .8 -F. -- ' ' d .' .= ' .v ' ..= . .
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n'~ 7 Tha last part is to seek additional funding. The E!
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- ! 9 g where the 'ac has supported the program with the industry and f: 10 E- our' commission in the past has been .against these programs. '
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i 372 I Ivan is jumoinc at the .;it.
2 OR. C ATT OU: I th!./.h the first one, r2 duca:. .; loc::ag
- is foolish, .
- ut as far as I can :all, ': L o c:'.a ge t 2 s t s ;ro tha 1
4 Only ones that ar2 rTiistic. I think Nhat tha G3rmans are s 5 i doing with that co-clanar 2:ss not reall'; =caaura up.
The 9
3 6' 4 natural circulation, is n ' t ?KL doing some of thati n .
R 7l l DR. S ULLIVAN: Yos.
I tt 3" 8I i CHAIRMAN PL2SSZTT: I was going to ask abcut that, d !
d 9 j
E PRI seems to be anthusiastic about that. Is Mos tinghouse a
b 10 E e nthusias tic?
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C2. SULLIVAN: To be frank about the problom, is r
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l that NRC mora or less coerced "10stingnous e into d0inc. the 16 i
$ natural circulation and probablf if we are spreading clame l
d 17 ' i 5 around, we should take a larg; share of the 31 ace. He >
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- realired when we were doing this, trying to get them to add 19 k the natural circulation to it--
20 j CHAI2 MAN ?L2SSETT: That is bef oro PZL did t?.cir 21 ll i experiments, I guess.
22 e--
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23 C2aI2:-1AN ?LCSS2TT : 30 that was not 30 unusual f:r 24 >
- v. ou to be kaen on it.
25
- 22. S ULLIVA;i: 3ut le Nore, in a managamo.:t sense, I
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- ALDERSON REPORTING COMPANY, INC.
l 373 I think, that rie realioed that we were taking out all'of the l
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' V 2' conservatism in tne funding picture. We just were taking the 3
, program right to the limit. And One problems that have been i 4I associated with tM 21-rod bundle have caused some problems l
i e 5i j li and we, there is just a cost overrun on the project.
e 6 o
g CHAIRMAN PLESSETT: Does anybody else want to make R. 7
- a comment?
. ?.!
5 8 N
CR. THECFANOCS : I was wondering if the sleeve d
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that you were using is introducing a rather large error in h 10 the simulation because if you consider the actual rod and E
11 E.c 3 the bulging flooding, the heat transfer from the red to the d 12 z
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s all of these drops and quench it very quickly and frcm then E 15 w
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- t l heated very well.
y 17 i w It is being heated well enough
=
a l DR. HCCHREITER:
. m 8 E and it does not cuench and it is probably 200 or 300 degrees 19 ,
i 6 below the rod temoerature. I
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DR . THE CF ANGUS : 0.X., anyway, I think this is a 21 matter of calculation and decending on how vou do te calcu-
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22 lati on .
What I want to say is, h: wever, that certainly 24 >,
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! 374 I l
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l there is going to c:<hibit a rather different quenching be- 1 I
2 havior than the sleeve that is making good around the rod. j i
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E OR . THE CFAMCUS : How thick is that?
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.e 11 0 CR. HCCHRZITOR: Well, it varies.
'd 12 l 55 DR. ':".E CF A UCUS : :n the ma:<imum?
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$ 14 I w at us get back to that poi::t 5- I CHAIRMAN PLCSSETT:
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r i s j that Harold is bringing up. Does anyone want to maha a s 5
T 16 i z c omme nt?
6 17 s It seems to me tnat you are going to have a li:tle
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5 trouble with the c ommission's view of tnat ganarai policy.
19 -I 8
n i They just do not like this kind of, well, they just do not 20 like to got this ,oartnership with industry as the other two 1 1
21 l 1
.oartners are industry.
22 l
. Tow , the only thing that you can say in response to 23 i
! that is that it is an :nacine or:::am so that there may be '
24 i l l 111 advised and poor financing and not to go tar:ugn that 25 ,
unlass vou f 2el varv wea:c about it yourself.
- ALDERSON REPORTING COMPANY. INC.
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l 9 I 375 17:1 DR. ZUDANS : Couldn't it be because it is directed
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3 CHAIR >DJi PLESSETT: No, I den st think that is really '
l 4 I the main point, unless Larry wants to comment particularly l
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i 4
S 6 MR. HOCHREITER : No, I don't.
l a 7 I think, from what I could read, from same of this -
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d safeguards un the program and I think the NRC has provided 9'
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h to more than adequate safeguards in the program, in terms of 3
5 11 looking over what Westinghcuse is doing, reviewing what a
d 12 Westinghouse is doing for the NRC. There is a grcup at INEL
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13 and EGG who are consultants to the NRC, who we interface with E
a 14 almost on a daily basis, who review all of our documents, U
! 15 all of our test plans, all of the test conditions that we i
j 16 run and the data . They are present for some of the tests, w
p 17 : not all of the tests , but some of the tes ts .
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]c 18 l CHAIRMAN PLESSETT: You mean frem the point of view 19 of Westinghouse getting an undue benefit?
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20 MR. HOCHREITER : Or whatever.
21 CHAIRMAN PLESSETT: Relative to other vendors?
22 MR. HCCHREIT2R: Or ehatever.
23l ,
So I think frem that point of view, . think there
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have been more than adequate saf aguards put On the program 25 l so there shculd be no question abcut the authenticity and the
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l l l' 376 1
- 0 ,! quality of the data that ecmes out in the program.
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2 i CHAIRMAN ?LESSETT : ' Jell, it does seen to be a pity.
3 It ne 11 that much =cney, particularly if you drop out 4 the na cura 1 eircula tion ces t , which might not be really a11 e, 5l ,
tha t necessary, unless they can .;et better and more e: tensive it t S 6 data than PKL.
e h 7i MR. HCCHREITER: I think we can.
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E n 8! CHAIRMAN PLESSETT: You do? In what direction?
d d 9 MR. HOCHREITER: 3eeter steam generator inforca-i tion.
h 10 t 5 l lm 11 ' DR. FABIC : May I make a ec==ent?
d 12 CHAIRMAN ?LESSETT : Yes.
E h 13 l DR. FABIC: ife were interes ted , not so much in the l
le 14 l natural circulation of the whole loop, because we don't have 2
a 15 ' any separate effects data on steam 3enerator, tihen a steam M
j 16 generator is heat removal rather than heat source, where you s
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have a condensation process going on, tha t opera tion with 3l l
@ 18 ! the steam generator there is no seoarate effects data in O
n g 19 l! e: tis tence agains t which to verify. 'Je have condensa tion in 20 i
the side tubes and the couple of view graphs that I shewed 21 i before, that Peter Grif fith has come up with, with the four 22 tubes indicates that we have a question.
23 ! CHAIRMAN ?LESSETT: ' Jell, you are thinking of tha 24 7g 513:: yatling7 25 , 7A3IC:
"2. That is ri gh t . tihera you are removing i
1 i
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l l l 377 17'3 3i heat to the secondary site, rather than adding from the secon-
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' l 2 ea=7-3 CHAIRMAN ?LISSETT : Right, but ?XL ran seme tests 4 vith that.
a 5l DR. FABIC : Not simple effects tests, enly 1:cp.
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n 3 CHAIRMAN PLESSETT: That is true, it was mera of e 6l!
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8 DR. FABIC : Right.
d d 9 DR. CATTON: The steam generator tests were with i
h 10 freon.
E 5 11 CHAIRMAN PLZSSETT : I think that--
a d 12 MR . SULLIVAN : The Flecht-seaset Program, the natura 7- s g C y 13 ! circulation part of it has been very carefully integrated into z
@ 14 a larger picture, both looking at the work that was dcne at s
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23l So the program has been structured to answer seme
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I l ALDERSON REPORTING COMPANY, INC.
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I 373 e
4 CRAIRMAN FLISSETT : Right.
9l I will say, let me try to shortan cur time allowed.
2 !
7
.\ side from questions of scme peliay tha t we don't
,, l need to be involved in, about jcining in with industry fer e 5l tests or tes t program, I don't see why it shouldn8t go on.
b se 6l ?ersonally, as to the policy, I don't see why it is so bad
- t j 7 to even do it with industry, even though they are a bunch
") 8 f bad guys, sometimes maybe , but they can have white hats I e
d 9 C00' I
i h 10 Tha t would be wha t I would say to you, Harold.
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11 FE . SULLIVAN : Le t me j us t summarise.
3 1 d
E 12 l We f ee l tha t the Flecht-Sease t program has provid-I h 13 5 ed an enormous amount of data and this program has been going K
la 14 on over several years and it has addressed a lot of issues 2
a 15 that have been brought up, being refloodee transfer and has
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19 l added at our insistence. So that part of the program is from X
20 , the NRC side, 21 The cost and schedule to the Frogrcm are currently 22 under consideration now, to address the shortccming of tha 23 ' funding that we have . The plans are s till consis tant to can-24 l clude the program, the testing part of the program in FY'2 25 ,
and conclude the analysis in 7Y?3.
l l ALDERSON REPORTING COMPANY,INC.
379 J7 5 jj CHAIRMAN PLESSETT: I think you've got the sense U 2 f "# 8 "Ui**"U "7" 7' 7
MR. SULLIVAN: I appreciate that. l CHAIRMAN PLESSETT: Nell, le t 's take a break and 4l e 5 le t's try to keep it short.
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s 6; Off the record.
. 1 !
j 7 i (A short recess was taken.) '
E 8 CHAIRMAN PLESSETT : On the record.
l d
- 5 9j Let us reconvene and Harold do you want to introduce z
10 the next presenter?
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la 11 l -
MR. SULLIVAN : Yes. The next presentation will be d
z 12 by GE on the SSTF Program. It is the program that is seme-
= l
( 3 13 i eimes referred to as the 30-degree sector program. I think l 14 tha t ought to be the next presentation. Mr. 3urnette from GE 2 15 will be making the presentation.
E j 16 As far as the steam explosien work we understand ;
d 17 tha t the guys are on the way, so maybe it will be the next 18 presenta tion , if they get here and we811 split either there E
19 or after lunch.
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20 STATEMENT OF JERRY BURNETTE 21 MR . BURNET'"E : Good morning, gentlemen. My name .,
l
, 22 is Jerry Burne tte.
23l As Harold indicated I will be speaking about the C
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BWR Refill /Reficod Program , which is also a cecpera tive 1
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l 380 l l
@ have divided my presentation into these three general cate-2i g rias and I think, as requested, I will speak to these three O 3
4 The program objectives, briefly stated, are to r
o 5 develop and improve an unders tanding of the phenomena that i
A d 6 controls the reflooding and refilling of the BUR.
o i .
{ 7 The second objective, really two parts , to develep -
8 and qualify best estimate LCCA Codes, to predict that LOCA d
3 9 behavior.
- i h 10 Third, to provide a basis for assessing the licen-E g 11 sing calculations, both the assumptions that are built into a
- J 12 l the licensing kinds of calculations, as well as to assess the h 13 margins that are inherent in those calculations.
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14 l The main elements of the program are summarized t:
! 15 here in my lef t column and a brief status indicated on the
! right.
j 16 ;
l 6 17 ! The core spray distribution task, as you see, was
!5 18 completed. It was done basically as a reconfirmation, using
=
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20 areas of tests under GE funding and, as indicated, tha t has 21l been completed, I believe early last year.
22 A single hea ted bundle task had three separa te cb-23 ; jectives. A series of system effects tasts had been complat-24 ed. A series of adiabatic injection technique develcoment 25 tests also have been completed and the puroose of those, !
i i l i ALDERSON REPORTING COMPANY, INC. l
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381 might briefly indicate , is to verify that the development and fl(7 3
'G) 2 verify that the procedure plan for use in the large 30-degree saction facility, wherein we injected steam to simulate the 3
4 nuclear fuel heat transfer effects, could, indeed, be done.
5 The third series of experiments, single heated sn b 6 bundle system, were specifically directed at developing some e :
y basic data to be used in the model development activity. -
7l ja I
~
8l The 30-degree Sector CCFL/ Refill system test has I
e d 9' been started, as indicated by Harold. The facility is 1cca-i h 10 ted in Lynn, Massachusetts. It is a full radius 30-degree 5
5 11 sector simulation of a BWR cere. In addition to that a:.1 d 12 of these surrounding regions of volumes are scaled to simu-Q 5 m
13 late the system effects. It is limited in its pressure j 14 capability to 150 PSI maximum pressure, so we will be looking 2 15 at the tail end of the LOCA during the low pressure demain, s l g 16 the refilling and reflooding of the system. l s
d 17 l CHAIRMAN PLESSETT: Where is Lynn relative to Bos-5
$ 18 l ton?
E 19 MR. BURNETTE: Lynn is roughly 12 miles north of 20 Boston.
21 The next task, as indicated, 360 Upper Plenum, a 22 mixing task. This would be reduced scale and the purpose of 23 ; this task is to verify that in running the e:<periments in a 24 30-degree seccor, as we planned here , tha : we haven': in:ro-25 duced any si;;nificant wall effects . The planned approach to ALDERSON REPORTING COMPANY,INC.
i j
380
- S 3 verify tha t, the 300, that the 30-degree sector was indeed 2
\
I adequate is to run the 360 first with its own little 30- O 3 degree sector in place, measure what gces en inside of its
- 4. cwn 30-degree sector. Then remove the sector, repeat the e
~ 5l experiment, take those same sets of measurements and compare
\
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e 6} the two, one on one, to verify tha t the presence of the 30-
{ 7 degree sector walls in the smaller scale facility did not 3
8 introduce any significant differences in the results.
i J
d 9 The design work for this facility will probably i
@ 10 start late this year.
E 5
< 11 The area of model development, and I should stress a
d 12 that this is related to the over all track effort working in 13 I conjunction with NRC. EG&G and the BifR track version. A a
l$ 14 number of basic models have been developed and I will speak 2 15 to those a little later. Some existing have been approved a
x j 16 and work has started on the single channel model effort.
S i g 17 { The third category is kind of a support task where 5 i h 10 we work with EG&G and have been working with them in the de-t 19 velopment of the preliminary version.
g n
l 20 l The model qualificatien task is the final task cnd, l l l l
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21 ; as indicated, that effort is just new getting underway, as we
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22 l are staring to--we have finished preliminary assessment of 23 '
some of the basic acdels and so we are going into a qualifica-24 tion phase for those preliminary models.
25 ' The three key e::pericantal :2sults to data, one in i
ALDERSON REPORTING COMPANY, INC.
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- 17:9 the area of core spray distribution and I will say a little
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4l adiaba tic injection technique is , indeed, adequate.
e 5 Then thirdly I vill have scmething to say abcut 7 i 5 6l' the system behavior that we cbserved in the system effects e
f7 test in the single heated bundles task. '
l 8; Regarding core spray distribution, the short series N 9 of experiments was done for individual nozzles for a raise i
h 10 of n z=les. Pretest predictions were made, based on those 3
5 11 re:ults, for the 30-degree sector experiments which was modi-d 12 fled to simulate the BWR core geometry and the experiments O$ @
5 2
13 were run and the comparlsons were =ade between the results of the experiments with the pretest predictions.
14 They, the
! 15 results were very good and, indeed 3 reconfirmed what had been j 16 shown in an earlier similar program using BWR six hardware z
g 17 and configuration. The results of this task have been dccu-N k 18 mented and that report has come out within the last few weeks, 5
19 I believe.
S n
20 Regarding the adiabatic injection tests. Our pro-21 cedure was to use an atmospheric pressure system which had a 22 single bundle and again all the related volumes that are 23l typical of the BWR system. We first ran the experiment using 24
( a heated bundle, measured the refilling in the core reg! n in 25 l l
I ALDERSON REPORTING COMPANY. INC.
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,10 1, the lower plenum. Removed the heated bundle, put in one of I i
l 2
the dummy bundles that we had designed to use in the Lynn f cility. Tock a crack at the steam generation in the 3
4l bundle. Programmed that into the unhea ted bundle. Repeated i
the experiment, again measured the refilling of the bundle g 5 9
j 6l i
in the core region of the lower plenum and, then, made a ene j 7 on one comparison of the refilling rates. Those refilling E 8 rates were very similar and we found that part of the reason n
d c 9 for that ws; that we didn't see, I underline did not see, any
- r:
h 10 very cyclic behavior where liquid entering the top of the 3
5 11 bundle would be vaporized, generate a lot of steam, therefore, D
d 12 change the operation point on CCFL characteristic curve, cut 13 off liquid for awhile and, then, once that puff of vapor had E I l 14 l gone up then go through the cycle again. We didn8t see that 2 15 a t all. There wns more or less a continuous drainage of g 16 liquid, as governed by the characteristics , CCFL character-g 17 i istic curve, the upper tie plate and the steam generation, s
@ 18 the heat release from the heated bundle was over a relatively -
0 l 19 long period of time. So it was a very slow movement on the g
n 10 CCFL characteristic curve.
I l 21 ' Very little feedback frcm heat generatien in the l 22 bundle to tue amount of liquid that's being drained through 23 the top.
24 Our conclusions were that or was that we, indeed, 25 could use this technique in the Lynn faci'.i'y ::o simulate the f
! ALDERSON REPORTING COMPANY, INC.
I 385 17:11 effects of fuel bundles through this steam injection tech-
/] 1 "i S l 2
S me f the results that we observed in the heated 3
i' 4
bundle system test, first of all what we find is that the 5
steam in the bypass region is condensed by injection of L?CI, s
a se 6 s that limits the amount of steam available at the top of
~
f7 the core, in the bypass region. So a lot of the liquid in -
!8 N
the upper plenum drains down through the bypass.
N 9 As soon as we have a liquid inventory in the bypass i '
h 10 that fluid can communicate to the bottom of the core thrcugh E
5 11 the so called leakage holes, bypass or flow path, and the d 12 bundle starts to develop frcm the bcttom of the bundle, tO !
V l= 13 ,
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upper plenum, down through the bypass and up frem the bottom.
E 14 l Also during this time there is some drainage thrcugh d i 5" 15 l t' top of the core, as limited by the CCFL characteristic
$ l j 16 of the upper tie plate.
us
] '
g 17 ; Once you have put enough ECC water in the upper N
{ 18 plenum the liquid there becomes subcooled and you get kind of 5
g 19 a breakdown phenomenon, and the bundle then fills the rest n
20 of the way up through its top .
21 The other interesting thing that we find is that 22 we actually, we see it in the data, we will see it in a 23 : similar set of data that I have from the two tast apparatus, O
V 24 i
but here again we find that we actually pull a level in the 25 ' lower plenum that continued vapor generation frem the flash-l l ALDERSON REPORTING COMPANY, INC.
1 1
I l 3c6 hl2 ; ing, limits the amount or the drainage rate frem the bundle 1
2 s we end up with several discreet levels in the system. A 3
level in the lower plenum, two-phased level in the mi::ture 4 leveled in the bundle and sc=e liquid in the upper plenum, e, 5 as well.
a s 6 So the water gets into the bundle rather quickly, e
N g 7 through the bypass and some drainage through the top and -
g 8 finally a breakdown and during this time it is being suppert-Q d
d 9 ed in the bundle by this CCFL condition at the inle t to the N
@ 10 bundle I guess, as indicated here, so we are able to ecm-5 j
a 11 pletely fill the bundle cere region before we fill up the 0 12 lower plenum, which is somewhat contrary to the normal fill-5 h 13 I ing sequence that envisioned and captured in the licensing a
l 14 calculations, where you start from the bottom and fill the E
2 15 system from the bottem up.
E j 16 In the area of modeling results, again these are w
6 17 the three general areas that I alluded to earlier and I will g 18 have a little to say about each of them. -
E g 19 DR. THE0FANOUS: Would you say hcw much time that n
20 is, roughly, between the filling of the bundle through these 21 bypasses at.d the filling of the icwor plenum? Of ccurse I 22 imagine you were going to have some standing there anyway.
23 Hcw much, roughly, is the ti=e involved there" 24 MR. BURNETTE : I did not hear the last of your 25 l question, but I will answer the first part.
1 \
l l ALDERSON REPORTING COMPANY. INC.
387 l
J.] 13 3 In the TLTA data that I will show you, in the (m / f llowing presentation, I will actually shew ycu 3:me data 2
3 and we can lock at it at the time, 5:t it is roughly in the 4 rder of 100 and 150 seconds :: fill the bundle back up.
e We find over the test duration tha t we ran, we never fill
-g N 5l s
a 6l the lower plenum all the way back up,
" ~
7 DR. THEOFANOUS: That is good enough.
E 8 MR . BURNETTE : In the area of basic models the a
d 5 9 initial evaluation of the weight distribution and the i
h 10 packages that were in the TRAC Code when applied to the BWR E
ja 11 flow regimes indicated that there was a definite i=provement 4 12 needed, so a new void fraction, a new package in the inter-
-~x j '
\ y 13 facial shear and friction was developed and was neu in there x
{ 14 and those preliminary comparisons indicats that we, indeed, E i 2
x 15 can predict the void distribution in the BWR flew regimes.
x g 16 Also some phase in velocity distribution affects s
d W
17 were in there and probably one of the most important things x
g 18 is tha t the new package accounts, adequa tely acccunts fer E
{n 19 CCFL condition that ceuld e:ist at any of the major flew 20 regimes.
21 In the area of interface and wall heat tra ns f e r ,
22 some of the improvements and some of the ccrrelations that 23l were in the code, a package was added en subccol boiling. A
)
. 24 package was also included for radiation heat transfer and a 25 i
- ritical quality, boiling rate correlation was also da"elcped )
l !
l ALDERSON REPORTING COMPANY, INC. !
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33 I
el4 ; or adapted ac tually, f or inclusion in the IRAC Cede .
2'
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- S2" # l U *3 #i'8 L' 2#=U ?f L=Er0""= "3 O 3
in the basic equaticns. ! suspect you heard abcut scme of 4 these yesterday, but seme improvements in the reversibla e 5 lesses. Improvements in both forward and reverse calcula-6 h 6 ti ns f the irreversible losses and included the ef fects of a :
f7 a void fraction gradient in the horiaontal flow.
Regarding some >f the 3WR specific component models.
l 8 J
d 9 Work in a couple of major areas. Fir s t the je t pump model i
$ 10 was developed and features of the model, I guess, are indi-E_
jD 11 l cated here. Momentum conservation, improvements made for p& 12 the Delta ? calculations for area changes and also modeling h 13 l of all of the mixing an'd other irreversible losses for all s :
ls 14 of the different fl:w possibilities. The je t pump is with
=
2 15 the drive and induced flow. There are lots of ccmbinacians w
z j 16 of flow directions for those two incoming streams, as well m
6 17 as the combined s treams leavin3 the je t pump.
w x
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18 In the area of the separator and dryer, somewhct 19 of a simplistic approach used to model those two toge ther ,
g ,
n 20 The model in there provides 100 per cent face separation and 21 dces a reasonable job of calculating the ccmbinad pressure 22 drop across the steam separators and the steam dryers.
23 ,
We just started in this third area of upper pl:num 24 modeling and what has been done so far 's very cruda. Right i 25 : new there is nothing that is suitable in the TRAC C:da and so i t
ALDERSON REPORTING COMPANY. INC.
339 15 this is the first step of users specifying the flew distribu-
)
(J7:?)
s_ ,/
2 ti n and tamperature cross the top of the upper planum for a
ca lcula tions , for feeding :he core region in cha calculations-3 l
4 i Turning now to the utilization of the results ,
i e 5 again, the first one talked about a recenfirmaticn Of the a'
9 8 6l .
methodology that is used currently in the licensing arena. !
$7 These others are more general in terms of longer reach appli- '
8 cation. One of understanding the pehnomena that controls d
d 9 the reflooding, refilling and the reflooding and also Scw i .
h 10 important the various phenomena are that CCFL at the top of
.i z
5 11 the bundle versus CCFL at the bottom of tha bundle.
m d DR. CATTCN: When you look at the CCFL at the top (g)
/
{12 a
13 of the bundle do you in'clude entrainment in the flee out of E
W 14 the bundle?
E 2 15 IG . BURNETTE : When we look a t it--normally, in a w
z j 16 CCFL condition there is a liquid continuum covering the e
restriction and a vapor continuum, essentially, ccming into i 17 x
z
- W 18 it.
=
4 19 DR. CATTON: Coming up out of the bundle is going g
n 20 to be steam with entrained water?
21 MR . B URETTE : Yes, right.
22 DR. CATTON: That is going to affect the CCFL?
23 gg, 3JRNEZ 2: Yes.
sm 24fI DR. CATTCN: Ycu do enhance the density to account 25l for the entrained liquid in the vapor flu:c?
l l ALDERSON REPORTING COMPANY, INC.
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l l
l 390 16 MR. BURNETTE: In the licensing calculations?
2 DR. CATTON: In any calcula tions . I am asking a O 3
question. I am jus t wondering, because you had talked a'ccut 4l dry steam earlier and I hind of missed what you were doing e 5 with the dry steam. If you were looking at CCFL for the
- i N l se 6I upper support plate with dry steam that may not be quite
- i
{ 7 proper. It cught to be, you cught to include some entrain- -
8 8 ment.
N d
5 9 MR. BURNETTE : Your observation is right and also, i
h 10 if there is any super-heating of the steam that also has to 3
5 11 be included, in calculating when the CCFL condition would m
d 12 break down, because tha t--
13 DR. CATTON: I think the biggest impact would be 5
l 14 the effect of the density of the mixture that is ecming up 2
W 15 l out of the core. Tha t might be more important than a little M
f 16 ; bit of the super-heat. In any event, I think you ought to e
i .
p 17 i be looking at tha t or that ought to be part of your calcula-w
=
5 18 tion.
E p 19 MR . BURNETTE : Yes, I agree, in the modeling.
20 DR. CATTON: And in the experiment.
21 If you are looking at CCFL on that 30-degree sector I
22 ! you ought to be putting a two-phase up from belcu, if you are i,
23 ' going to be looking at CCFL properly.
24 >E . BURNETTE : The 30-degrae sector is in: ended 25 ! primarily for model qualification.
l ALDERSON REPORTING COMPANY. INC.
391 17:17 DR. CATTON: It is the spray cone, right?
I
/
C] 2 MR* SCRNETTs I'" 3 #=7*
3 DR. CATTON: The 30-degree sector is primarily for 4l the spray cone? j l I e 5 12. BURNETTE: The 30-degree sec tor was built for 9
j 6l tw purp ses. One to do spray distribution tests with an R
- a. 7 empty cover, upper plenum, if you will, a vapor continuum. -
f8
'J It was also designed so tha t we could do these kinds of e:(-
d 9 periments that we are ncv starting to do, the refilling, the i
h 10 reflooding type of experiments.
E ja 11 DR. CATTON: But if you are looking at CCFL at d
z 12 that facility you should be looking at somethin:; other than N
] 13 , dry steam or as well as' dry s team.
@ 14 FR. BURNETTE : I don 't disa:;ree , but my point is--
a E 15 DR. CATTON: But you don't seem to cgree either.
j 16 MR . BURNETTE : My point is that the facility, the s
d 17 data from the facility is being used primarily fer model
. 5 18 qualification.
c 19 DR. CATTON: So your only--
20 MR. BURNETTE: We will be applying the models that 21 are being developed from other data to verify that they can 22 or cannot predict the behavior tha t we observed in the 30-23 : degree sec tor.
.,r 24 ;
DR. CATTON: I guess to me, then, there is a dis-25 ;
connec t between what you are doing and what you are doing and I
ALDERSON REPORTING COMPANY, INC.
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392 i
- 13 j i what you may expect in an actual applica tion of the codes .
2l MR . BURNETTE : The same kind of disconnect, Ithink,0 3; that ue discussed earlier, where :he simulator facili:ies 4 ! don't have all of the phencmena tha t you have to properly
?,
e 5l account for in your after prediction.
5 !
3 o 6 For example, in this facility the rods are unhea ted.
E 7 The steam is injected. It, indeed, would be dry steam so -
[ 8 when we are verifying or qualifying our model to predict d
d 9! l CCFL in a multi-dimensional facility such as this we have to 3-
@ 10 : qualify it in the sense tha t we verify or qualify, whatever 3
5 11 word you like, our ability to predict these kinds of condi-a d 12 tions and they may, indeed, or would, indeed, have to be 13 modified. The models would have to be modified to include a
j 14 the effects of the entrainment.
2 w
15 DR. CATTON: And that means tha t your models will
=
g 16 l not be qualified for licensing?
- i d 17 i FE . BURNETTE : Tha t's right , specifically.
m 18 DR. CATTON: Is tha t right, Harold, or am I running 3
c 19 down the wrong track?
h n
20 CHAIRMAN PLESSETT : Unless they show tha t it is 21 conservative, what they are doing.
22 DR. CATTON: Well, if you are using dry s team a t 23l CC7L you are not going to be conservative.
24l CHAIRMAN PLESSETT : Then we have trouble.
25 ' DR. CATTON: I t hink s o .
l l ALDERSON REPORTING COMPANY. INC.
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,93 L 17:19 CHAIRMAN PLESSETT: In one sense it is conserva-l t
7-~
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s_ 2j tive and in another sense-it isn't.
1 3 DR. CATTON: As far as the spray distribution is i
4l concerned it is probably conservative, but as far as CCFL e 5 is concerned it probably is not.
ri i e
N 6i MR. SULLIVAN: Jerry, has this been brought up in f7 !
the meetings before?
E 8, MR . BURNETTE : It has not specifically, and pri-i J
g 9l' marily because there has been a fairly sharp line divided i !
$ 10 ! between program work and utilization of the results in the i i
!< 11 ' licensing.
a J 12 CHAIRMAN PL2SSETT: Yes.
3-6
' E 13 i DR. FABIC : My recollection of the original f ormu-
$ 14 l lation and plans for this particular facility included the C-l 2
3 15 introduction of spray with s team from the core , going up . I
' \
a 16 Has this been abandoned? ,
A i d 17 DR. CATTON: It sounds like it.
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E 18 l DR. FABIC: So there was, so, therefore, there will
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$. 19 ! be an answer to your ques tion. It is not just sure steam I
20 l being injected upward to the core, but also spray, entrain-21l nent.
22 5 'E. BURCETTE:
It was never planned. I t un s a =40-23 ' phase _. ,
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24 ! CHAIRMAN ?LZSSETT: Me dcesn 't have that . ;
25 , DR . CATT0'!: He dcean i t a gree .
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i 394 20 1; DR. FABIC : Then there was a change of plan?
1 \
2i S . BURNETTE : No change of plans.
I 3l CHAIRMAN PLESSEN : He said it was never that way. ,
l 4l MR . BURNETTE : If I am unceratanding your under- !
, e standing that there was going to be a tuc phase mi::ture in-vi 6 jected into the core region to si=ula te the effects of e
N 7, bundle heat transfer.
- I I
N 8
I DR. FABIC : No, to simulate the entrainment.
J d 9 DR. THEOFANCUS: Are you using the flow race, mass i
E 10 flow rate or velocity? Wha t is your basis fer injecting the E
5 11 ' stesn? Because, if you are using mass flow rate you are a !
4 12 , conservative. If you are using, if you are trying to model a
=
$ 13 this sprcy, in other words , only with velocity then you have 5
j 14 ; prob lems . Uhat are you using? What basis will you decide c
2 15 ; wha t flow to put thrcugh the bundle upward? Hew do you de-6_
j 16 ; cide to use steam flow in there anyway? Is it mass or is it e
p z
17 velocity you are trying to match or are you matchir' a ny?
~
E 18 l MR. BURNETTE: Le t me give you a little background.; .
r ! l
$ 19 ! I will try to answer that specifically. !
a >
l i 20 l i
The approach for the reference, if you will, candi-j ,
I 21f tisn is to use the measured condition frcm the two-loop 1
22 ' tast apparatus. Lock at the amount of heat in this tra ns f e r ,l l
23 that is trsnsferred from the fuel bundla to the fluid ever, ;
I 24 which occurs over a relatively long peried of time. Calcu- !
f 25 lata how nuch vapor tha t Seat would generate and then a pro-I i i
i
- ALDERSON REPORTING COMPANY. INC. !
395 17:21 gram in that amount, over that same amount of time . The
/T 3l
. ( ,/ 2I runction changes, but it is very sica, it is a very sicwly I
changing function. So it wculd b, done en the basis of 3l ,
I 4l 3 mass calcula tion .
5l DR. CATTON: Yes, but it is nass based on heat c
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a 6l transfer. If you have a carry over it will be too icw.
I :
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DR. WU: It seems to be an energy based criteria.
5 8 DR. CATTON: That's right.
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c 9i CHAIRMAN PLESSETT: Right.
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E 10 ' Well, I think we shculd spend seme time here new, E ,
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13 12. SULLIVAN: Yes , I think tha t is a goed point.
g 14 I Were the injections designed in the original pro-i b
_ j E 15 ' posal to include an injection of water, along with the steam?
a .
= i j MR . BURNETTE : I think it is possible to do that, ;
16 l d 17 ' but there was never any intent to introduce anything more E
}: 18 i
than the dry saturated steam.
b g
19 DR. CATTON: My unders tanding of the Original pro- ;
n , >
l 20 ! gram is that it was just spray distribution and then I did 21 l not pay any attention for quits awhile and it is just new 22 that I see tha t they are also 1 coking at C07L. It might be j 23 ' tha t that is sert of a tack on that was never planned.
24 CHAIRMAN ?LESSETT : I can't see how they can logi-I
- s. 1 25 i j cally separata it any way.
. ALDERSON REPORTING COMPANY. INC. l
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62 ; DR. CATTON: You can just sort of catch it in i bucke ts .
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'f asi s 1 3R. 3URNETTE: Physically what is going to happen s,
2 in the delant facility is that we inject dry stesa and i
3l there will be drainage through tne top of the core. Scte i
4l ;
of that drainage will be entrained and carried back upwards. - ,
e 5 3R. CATTCN: If you are going to try and :le 1:
9 I h 6 to a codel, don't you have to know what it is?
e ,
f 7l CEAIRMAN PLESSETT: I think we had better leave it fn 8; at that. I think that =y impression was the same as Dr.
e i d 9j Catton's. You really are just studying spray distribution.
i l
$ 10 l Now, if they are going beyond that, they should be a little 5
5 11 careful about how they use it. Maybe we can leave it at a
d 12 that, Harold, and go on. That is a change in our perception z
=
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s 13 l anyway, e
E 14 LR. CATTON: But that nay juct be no: paying w
t
? 15 , attention to all the problems.
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.' 16 CEAIRMAN PLESSETT: ' dell, we are not blacing a
e .
p 17 : anybody. "de will take some blame, teo, as far as that a
. 5 18l'i i
goes. '
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19 i LR. BURNETTE: I guess, coming down the lis n ;
20 again, it would be second or third utilization was to !
i assess the evaluation methods, both, again, the ascucptionc 21 l l
22 j in the margin that you would get in using those methods.
l 23 The progra: is generating data for bes; esti= ate acdel de-
[\ 24 ; velopment, as well as a separate activity for tha odel l i
25 ., developcent. Finally, it is the inten; to use data frc: this i i '
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ALDERSON REPORTING COMPANY, INC, I 1
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_ _ . _ _, _ . . _ _ . ..,-,--v_., , , , - . ,
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2 prograc, and other data , to qualify these best-esticate ;
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3j CHAIRMAN ?L2SSITT: Eces tha Oc plete ycu. ,
4ll presen ta tion?
f e 5 DR. LURN2TT2: Tes, ths; is 27 presenta tion. 71me.
n N '
3 e 6i CEAIRMAN PL2SS2TT: Let me cake a coccont first, '
R -
8 7 in connection with the point we were just discucsias. 22-n 8! l sucably you will have a chance to find out what the Japanese' l
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=; 9i are getting in their spray test facility, which, in many l z- :
i
@ 10 l ways, sounds similar to this,, 360 degrees with air, 30 E
j degrees with steam. They have also c udied in some detail !
11 l a ,
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l 12 ; the behavior of the dronlets in the sprav. The trajectorica a'i
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j 13 l droplete coclecce and that affects the trajectories and thing
=
a 14 ,i like that. It night heln. in connection wi-h this Point 2 H ,
, I, 2 15 , that we havo just brought up. l a ,
= l l g' 16 l, DR. ZUDAN: During the presentation, you described ;
s y 17 what you are doing in the cc=ponents area and you said that 5
c g 18 upper plenum is just the beginning and that the users of l I
I 19 ; TRAC will have to specify flow distribution. 'iha t does it e
n 20 l really naan in terms of TRAC users?
i 21 , OR. 3URNITT2: To me y interpreta tion of wha l s
22l that means is there is a definite need to develon. a coce.re- !
)
l 23 hensive upper plenum model to be used in the IRAC prograc. l 24 'cle have had discussions with NRC and with Z3&G and ave a 25 proposal now on the table to go further in an upper plenun l
ALDERSON REPORTING COMPANY. INC. i 1
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i l 399 l
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-- 2j uR. ZUDAN: But does it really =eaa that the 1
3l !
TRAC 3WR code as it stands now is not ucablo becauue cow 4I can you specify flow distribution in the upper plenun?
e 5; '
LR. 3 URN 2TTE: I would no draw your first con-N 3
e 6 clusion. I would say it is not usable. This is an attempt ,
- k i
$ 7 to overcome a tenporary shortcoming that there is, and - ;.
. n j- 8, correct ce if I am wrong, is there is not a good upper plenut l ,
a ,
d 9l cixing model in any of the TRAC code z,
10 i DR. FA3IC: This 9uestion was raised with code 3 l i f3 11 developments bec1use we have known of GE's reservations
'4 about codeling of the upper plonus. I have asked them i z- 12 l ,
, a 13 whether they felt there'was a significant chortcocing in s~ _e 14 I
$ the code in that area so it shouldn't be released to the w !
2 15 public for independent assessment before that is fixed.
E i
i g 16 l The answer, and they are here and you can ask them, the x '
d 17 answer was that, to their knowledge, there wasn ' t anything w ,
=
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. w 18 , there that is obviously wrong, that the weaknesses as far
=
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$ 19 li ,
as the mixing codel are concerned, are not very clearly a i 20 identified and it =ay be worthwhile to let the code try i
cr attecpt to make these calculations before we star; 21l i
22 another development of a better mixing =achine.
23 3R. ?I2SSETT:
That scunds like a reasonable
(~~ 24 l .gy::gry, 25 Can we go on to the next itet?
i l ALDERSON REPORTING COMPANY,INC.
1 1
! 1 l 400 l i i I
i L3s4 1 DR. SULLI7AU: This is the conclusions to that.
l 2l Again, I would like to reitera e it is a corporate 3l progras between NRC, 2232 and the General Electric Cocpany.
i 4' The status of the program to date is that the spray dia-i e 5 tribution test has been ccepleted, the single heated bundle 9
@ 6l reflood test has been cocpleted. We consider this to be a
- l j
$ 7; very i=portant part of the program because it is the portio 6 l
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g 8- of the program at which we get the standing rates to put ;
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O 9i into the 30 degree sector. It is a very similar problem i E l
@ 10 l to what the Germans are going to face with their upper l s i
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plenum when they start running their upper plenu: testa.
l g 12 l The 30 degree sector is in the shakedown and we have some
=, l
@ 13 preliminary models for the 3WR TRAC code.
= ,
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5 ! I think 1; is also important that you realize there b
t 2 15 is part of the 3WR TRAC development that la actually in w i
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g 16 Il this program. They are actually doing suce of the codel d 17 development for it. ZG&G is reviewing that and including ,
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=
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it into the TRAC program. We believe that the resulta are l
= l ,
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" I 19 applicable to look at the methodology that G3 has used in g ;
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i 20 ! the licensing area to develou their snray distribution and l 21 ! the spray distributien and penetration in the upper plenut.
i 22 ; We also think that the data is, in terms of experiten;al 23 data , will help the assess =ent and the develop ent of the 24 ; 3WR TRAC code. 'le are also addressing s:=e interests tha:
25 l have been expressed by NRR in the culti-dimensional effects 4
ALDERSON REPORTING COMPANY, INC.
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'l in the upper plenum.in a 3WR during the spray period.
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We also believe that the results are applicable l
- 2. li 3-! to both the large-break and to the stall-break period in 4
~- a BWR.
1 g
n 5l The oeople tha; are going to do th: 0:00c explauiar
$ 6! '
experi=ent presentations have not shown up. 'is have a
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choice of going to lunch.
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CHAIRMAN ?LESSITT: No, I think we can go on with d
9
~. what we had scheduled.
E i C 10 '
O z l DR. SULLIVAN: The TLTA is up next.
= I a
II l i CHAIRMAN PL2SSETT: Yes.
j 12 j DR. BURNETTE: The bicwdown ICO Prograc is also
=
O j 13 '
cooperatively funded by NRC, IPRI and G3. I will try und 3
?e 14 <i 1
give you the sa:e kind of cuc=ary presentation that I made j= 15 I
on the refill-refloed program. In addition o the three j 16 general area of the presentation, overview, results and s
17 application, I will also have a separate area describing the
= -
- 18 l current plan for upgrading the TITA. l
- i
" i 8 19 ! The stated objectives of the 3D/ZCC program n
20 are to obtain general inforection fro: a systens kind of l 21l experiment on the over-all thermal-hydraulic and bundle hest ,
22 I i transfer during si=ulated LOCA, both larga and 3:311 breaks i I
23 '
included. Secondly, to provide a basis f:: assessing the !!
24 i i
! assumptions and the over-all nargins inheren; in the licensin 25 coces.
,i l
! i i ALDERSON REPORTING COMPANY. INC. '
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i n - - - - . _ , . . - , , - . . .m - _. , - - _ _ , _ , ...w , ,, .4
i l, l 402 i
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3R. CATTON: With resnect to your second objective, .
I 2: :nere are neat loss effects and scaling effects and all sorts i i j
I 3 Of things that make TLIA not really a simulated 35R. Are i I i 4 you going to tell us a little bi about how you accot cdate :
i i i
e 5l these problems in ge::ing to your second objective? j n
3 e 6i 2R. 3URNETTE: I would like to clarify the second !
R -
7
$ objective a bit. Because of the NRC funding of the re-s 1
p, 8 search, this gets into applications, the key word in the i.
O i
- 9i second objective is the basis for this assess =ent. In the j z
O
- 5 10 program we did not get into the specifics of evaluating the x ,
= i G
11 . various assucotions.
- l i
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0 z 12 ! 3R. CATTON: So what vou do is run a piece of l
, i E 13 y equipment, *ou generate'a bunch of data and it is for others
=
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to worry about the transition?
e j
i 15 3R. BURNETTE: GE.
- l l j 16 ; CEAIRMAN PL2SSETT: It has to be that way be-
- i 4
i 17 f cause NRC can't participate in a prograc which f acilitates z_
18 the licensing of 3WR's. -
w ,
s I
i g 19 l 3R. CATTON: 0.K. I should ask that question of n ,
20 l Harold.
I 21 ; 3R. 3URNETTE: 3ut your poin: is well taken in ;
li !
22] that in the evaluation of the facilitias it is incutben; f 23 unon us to evaluate heat-loss effects, other differences 24 fro: the reactor so there is, indeed, reascnable basis to i
25l, make these comparisons. l I
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- ALDERSON REPORTING COMPANY, INC. I
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, 13: 7 1 DR. PLES3ETT:
This is one of the problems with
( .
2l joint programs. You can see why.the Co::issioners have i
3l raised their eyebrows on these things, righ:? ,
t I
4! DR. SULLIVAU: Yes. There is an assesscen; !
e 5 -program in the NRC area , but we would not pay for the as-9 '
se 6! sesscent of the G3 evaluation codes. Thev are used for
. w E 7 licensing of the plants.
D !
5 N
8l DR. CATTON: I understand.
J i d 9-l LR. PLESSETT: Go ahead.
I i 5 10 { DR. 3URNETTE: About the specifics of the pro-z !
=
j 11 $ ram, we are using the two-loop tect apparatus, which, I a
p 12 j think, many of you are quite faciliar with. We have been
(~Ni .:
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m 13 using it, although ther's have been a nu=ber of i=provocents z
5 14 sade, over many years. It is a complete integral systees
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- I g 15 : test in the sense that we start at full pressure full power E_
j 16 conditions. All the components that we think are significan A
d 17 i in influencing the LOCA are there, all the ECC systems, all E i n I g 18ll the 3WR regions, 3WR cocponents are there. i n i 19 l We use a full sise bundle. We have used both n '
20 l 7X7 field design in an earlier program and in this one it i
1 21l comes on to 3X3. We have codified the facility so that it j 22 l i
is initially scaled to the 3WR/4 systet. It has been since }i 23 < changed to scale the 3WR/6 systet. l
[ 24 i We have locked at variations in the ICC systet Q ,l) 25 fro: the 3WR/4, the 3WR/6's, and how the full cc ple ent of f t
i i l 1
ALDERSON REPORTING COMPANY. INC. i
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i 404
'd:9 1 those systecs cocked un. i 2l i For a num'cer of years , particularly recen tly , the I
3l focus has been on the small break LOCA's. I have scte i 4l !
results to show you from the scall break tests. .
, i, t i g 5 j The recent results fall in these general cata-
? : '
j 6 gories. Soce improvecents were made to the facility in '
R :
l
$ 7 tercs of simulating the 3WR. This is over the last couple 'i j
8; of years and over the last year we have also codified the l e
9' facility so that we could run some stall break experiments ,
3- i g
z 10 4
and also have done acce separate effects inventory transient l -
- i j 11 j '
kincs of tests, coccenly called boil-off tests, where we j a
jA 12 l t
slowly vaporise the licuid covering the bundle, allow it to !
i j 13 ' uncover, and one of the' experiments actually turned an 20C -
a > ,
z l 5 14 ,
system on to reflood the bundle. ;
b l
_2 15 ! Sece of the cost significan findings, I think, a 1
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findings. The one I centioned in the other discussion that d
" l i
G 18 ,
the counter current flow limiting condition at the bottoc -
r i a 19 l of the bundle supports the two-phase inventory in the core n
20 and enhances the effectiveness of the ICC systet. )
l 21 Secondly, we have found that as we made improve-22 ' cents in simulation that the previous findings were again 23 reconfirced. In all cases, as you would hope, the ICC 24 . systems are effective in cooling the bundle. This third 25 activity being outside the prograt done typically by GI I
ALDERSON REPORTING COMPANY,INC.
-.. . . . - --. . . - . - . .-. . =
l t
405 1 alone, that licensing predictions have been cade for the 7-(329 t
l 2I experi=ents and co: pared and have de=cnstrated .a substantial 3 over-all =argin in calculation of peak clading temperatures.
i I
4! I have sace results from a recent large-break !'
I e 5 simulation. These are the conditions for the test. 'ie
, I 9 , l 3 6l simulated the average power bundle, se; the spray conditions R
& 7 at the average flow rates of nominal temperature condi:icus,-
n j
8 used the best esticate for the power progratting :o the d
9 9 heater bundle. I cight say that the approach used over-all
?
5 10 } in conducting these experiments is to run the on a best-3 l l
B 11l efforts, best-esticates . basic so we know re: hor than uix i 12 l licensing space with what is reality.
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13 With regard t'o the cost recent, I guess it is the
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'A 5 14 l '
'973 ANS power decay curve to calculate the power to the h
E w
15 bundle.
= 1 g 16 Finally, in this saries, we included the cocewhat
- I 6
w 17 l.
fairly recent bypass leakage flow path between the bottom ,
x ,
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g 18 of the fuel bundles to the bypass region, the so-called j P l r
a 19 l bypass leakage ho a e , and included that in our simulation.
n 20 , CEAIRMAN ?L3SS2TT: Will somebody help ne? This 21 13 the 1978 ANS power decay. Has it been reduced a little 22 ; bit since then further? I 23 1
DR. SULLI7AN: Yes.
N 24 i
, s i CEAIRMAN ?LISS20T: That is what I thought.
I \- /
25 '
- DR. SULLI7AN
- There is a new ANS and my recollec-l 1 !
i ALDERSON REPORTING COMPANY, INC. l
j I l l
l 406 l 4
I I
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tion is that the old one is about 2 or 3 ner cent, but it l t, i 2! varies. l I
3i CEAIRMAN PLISSITT: It varies in different tice 4l periods. I just thought you might rece=ber the detail. I e 5t thou ght it would be at AUS plus seven, is what it really 9
@ 6 is, or real decay curve plus seven or sacething like tham. ;
R ; , -
$ 7' I was just trying to reassure ey setory. j e.
j 8{ DR. 3 URN 3TTE: We typically run tests both peak l J i ;
% 9. power and average power to get variations in over-all power E . !
5 10 ; performance, but also way back we ran sace sensitivity 5
j 11i studies on the effects of the decay levels when you cece B I down and have detersined the sensitivity in that region.
i_ 12 l ,
$ ! 1 13 i So I think we are fairly clean in terms of havind the data !
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= i g 15 This is a schematic of the two-loop test apparatus '
j 16 l and, briefly, I will hit the highlights. Full size , full s '
17
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power bundle, two internally counted jet pucps, each driven 1
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1 G 18 ! by an external recirculation loop. Internal steam genera- -
l
- i
- I h 19 l tion, of course, in the bundle, upper plenum rocked up, n i 20 ! steam separation, then the steam separator, full complecent i
21 of the ICC pumps, feedwater systec which we typically have i
22 used only for initialization, capability to simula te either 23 steat line breaks or recirc line breaks, either doubla-24 ended or single-ended. Then, again, the main change, the 25l :ost recent change highlighted here, the connection be veen l
ALDERSON REPORTING COMPANY, INC.
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l l 407 l i 1
_s 13 *11 1 the bottom of the bypass region and the bottom of the ll l N~ 2l- plenum. l; l
3 On this figure I have some level data, level i i i 4! versus time for three major regions. For reference I have :
l 1 i
n 5 a schecatic of the apparatus over here (indicating). Level l l 9 ! I j 6 and lower plenum. Opposite that er obove that the level i
. g ;
$ 7 in core region of the bundle, then,-of course, the upper
. n j' 8 plenum level.
l "J
9 9it Quickly going through the scenario, during the !
3
$ 10 initial part of the blowdown some depletion of inventory 3
i .
j 11 < from the--actually to the level in the upper plenum. A s
y 12 j little ways into the transient flow level in the lower plenun C 3
( g 13 !
{
See the effects of lowe.r plenue flashing, building up the l
2 5 14 ! bundle again. Right af ter -he lower plenum liashing is l
$ ! i 2 15 l when we stort to pull this level at the lower plenut. !
E y 16 Notice that a t this ti=e , shortly after the high prescure i A l .
d 17 1 core spray systems cace on, not necessarily related, but !
x ,
w
. o 18 ' shortly after, the level in the bundle drops rather cic- i n I e -
g 19 nificantly and what has triggered that is the level in the l l
n .
I .
20 lower plenum has dropped to uncover the jot pucp. So es- ll 21 ; sentially all the vapor tha; was being generated in the 10wer i
22 plenum before was rising and going through the core region. I 23
- Tow when the level drops beneath the je: pucps, tha; path is 24 l no longer sealed off. So cuch of the vapor is -hen sucked 25 ,
through the jet pucps and out the break. .is seen as tha; l i
ALDERSON REPORTING COMPANY, INC.
l j 20 8 1
t !
E3:12 1 hatpens, the ci:::ure in the bundle drains rather rapidly.
l !
i 2i Tou can see it staya drained for ecce 30 seconda or 50, :O I
3I seconds, sece:hing like that. During thia tice, there is l
t 4i continued drainage froc the upper plenue as governed cy the g 5; characteristic of the upper :1e plate, but tha t liquid n '
N i j
6l generally runs right on through with no accucula ica.
n E'
7i About this time in the transient after the low- ,
l A
j 8' pressure systecs have come on, the L?CI system has condensed !
d <
= 9! cuch of the steam in the bypasa so tha there is a rather z'
5 10 sudden drop in the inventory in the plenut. If you look l z
= ,
l j 11 j at the level in the bypass, you see i; filling in this I a i j
l '
- j 12 l same ticefrace. So the bypasa fills rather quickly and then
$ 13 l it otarta through a conoceter kind of effect, a:arta feeding >
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$ 14 l w
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liquid into the bundle throur_h the bottoc. So the inventar.v' t e i R 15 ; in the--you see an accuculaticn of inventory in the bundle e
i j
16; at this time.
A l
- b. 17 . Some tice later we have injected enough of the low ' -
5 i
M 18 l temperature 200 fluid to get a CCFL breakdown and along F_ \
s !
l g 19 l about this time the bundle fills rapidly from the top drain-
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20 age of the upper plenus to the top of the bundle. Sc, you 21 ! see, relative to an earlier question, the bundle ia complete- j
! l 22 ; ly reflooded secewhere at 'he il2nd ticefrace.
23 I have scoe tecperature data frec the sace test.
24 Io give you an indication of how mild these transien a are 25 tempera turewice, you see tecpera tures typically in the 700 ALDERSON REPORTING COMPANY, INC. I 1
1
I r
\
ma wvs 13: 13 1, degree ? range. At peak pcwer tests they run a little
- 2 higher up. This poin here (indicating) corresponds to 3, when the'1evel compress care crashing through :he bundle 4 on the earlier side, then folicwed by heat-up, then sc=e i
e-5; continued cooling from the top and reficeding from the i I 9 t 3
o 6I bottoc in this period (indicating). Then finally the I 1
. n 6 7 bundle is completely reflooded about here (indicating).
N j 8 Notice that later on in the transient we ge: th: tae teasure a
d 9 subcooled fluids clear down, way down. Midway down the I
@ 10 bundle you see scoe indication of subcooled 200 fluid all E
h 11 the way down on the heater temperature rise, the heater rod a
d 12 tempera ture.
z
% 5 I 13 i ER. TH2NFANOUS: Would you expect this to be also uJ g j 14 ' for a culti-channel situation with this icwer plenus or not?
E j= 15 DR. BURUETTI: I think it would, yes.
g 16 DR. THENFANOUS: If this fills at a different tice A
U 17 ' than you expect it--
x 1
= i
{c 18 DR. 3URNETTE: I would expect it to be dif ferent.
s 19 DR. TEEN?AN0US: You would have instability.
g n
20 Therefore, a tendency to fill the icwer plenun uuch, cuch 21 more than you are observing in this single situation. ,
i 22 l DR. 3URNITT3: Certainly -he bundles would be !'
f .
I 23 draining at different rates in a cui:1ple bundle ge etry, j but I would not anticipate -hat the level would c:ce up and I 24l 25 i seal off the jet pump as it did here. Cur lynn experitern f I
i i
l ALDERSON REPORTING COMPANY,INC. 1
410
$s14 ,
should show that.
CHAI?lWT ?L2SSETT: I think ths; 2hecfun aua '
3: speculation about the plenue filling up a lit:la aconer 4l s unds right.
e 5 DR. UR'TETT3 : I will turn now to so=e results n,
o of a stall-break test. We actually ran two. I ac talking e 6 f-w 7l t r
about the more interesting results fro = the second one.
~
E 8 This one, again, was average ;cwer. In this case, because
" 1 J
= 9 the first test was no ao interesting, we ran this with F
$ 10 ! further degraded conditions and didn 't use the high-pressure i_
3 jj , feedwater system and this one didn't use the high-pressure
< i 3 !
= 12 ' core spray syste . We did, in fact, use both the low a
= :
$ 13 ' pressure 200 systcas.
e_
$ 14 j This is a calculation cocparison down outside the a ,
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2 15 ; -
program. These were presented in support of the Operator
=
J 16 8' aid elines used da ta from the prograt. I thought I would w :
g j7 ' like to spend just a few minutes talking about. .
a ,
2 l
$ 18 l This is level prediction versus tice, ;#o level .
- i C l t 19 ' ou tside the shroud. The calculation of the data shown X
M .
20 l here just out to the peint of opening the A3S cr activa-ing i
21 ' the ADS system. On the inside level, the data is generally 22 above the calculation. Then the prediction is shown also.
1
[
l 23 A couple of key points to =ake, I gu e s s , is tha 24 the licensing calculation apparently did a pre :7 darn good 25 job in predicting the level right on the data with jus: a 1
1 ALDERSON REPORTING COMPANY, INC.
i 411
-LS 15 1 very minor difference here initially. The inside level 1 \
\~ l 2 of the licensing calculation under predicted the data a l i l
! 3j little bit here (indicating) initially and rather sub- i' I
4-l stantially later on (indicating). The key point for the ,
i g 5: . operator guideline application was tha t the--during this j s !
@ 6l (indicating) period of time the outside level is used con-R :
$ 7 servatively to say what the 2evel inside the shroud is, M
j I 8 what the level above the core region might be. l d
y 9 Again, thic calculation can be concervatively
?
E 10 used as a prediction of what is inside the shroud.
z
=
j 11- The large difference you see out here (indicating) ' '
a f= 12 in this region is due to this CCFL characteristic that we s j 13 i talked about earlier. 'After ADS the blowdown progresses
=
$ 14 rather rapidly. Flashing rates are high. A lot of steam t
E 15 la generated in the lower plenum. Again you get a CCFL w
=
g 16 condition in the bundle, as we saw in sete of the other s
. d, 17 ' data.
That CCFL condition is what keeps the mixture level x
18
{n high in the experiment. The analysis doesn 't take credit {
$ 19 for any CCFL. The c7re inlet lets all the liquid drain l A
l 20 through the bundle, accumulate in the lower plenut so the l I
21 - lavel is calculated, it would be muda icwer in the predic- !'
l i i t 22 i ' ion. !
l 1
l 23 ' A second crediction is also shown on here.
~ This !
(\ 24l '
13 a safe calculation. In the licensing applica icn we use 25j a cocbination of safe and reficod. Reflood has the further ,
d ;
I
.i ALDERSON REPORTING COMPANY, INC. l
l l
l 412 t
f i i l
18:16 Ilj conservative assucption where soce of the ICC water is I i
2' neglected and so in the safe ref10cd Appendix I kind of l
3l calculation the level even ge:3 significan:17 icwer.
4 It was this licensing calculation through safe e 5 e
D I
and reficod that is used to n.redict the n.eak clad t erc. era -
3' 6 i tures and help in the prediction of tecperatures as well.
-7 ,
=
" 7'!
- As you might guess, with the bundle staying covered through- !
M i
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E 8 M out the transient, no heat-up was observed at all in the u ;
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x 9, experiment, bundle tecperatures following the fluid sa tura-
- } ; ,
10 I
$ tion te=pera ture. i
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Licensing calculation, as coon as the top of the !
s t f"
12 l core is predicted to cover, calculate hea tup, then tha t, l q
1 13 '
I of course, turned around af ter the bundle was cocpletelv E 14 ' l g l reflooded. i
= i 9 15 '
g j Turning now to application of the data, you have j i i 16 '
y i seen some already, but, in general, we think the expericents 17 d"
F havecontinuedtoimproveourunderstandingofthephencenal l
5 18 ,
- ! particularly the governing phenocena. Again through the l
- 5
.- t 19 t e l kinds of comparisons you have seen, we have established I l
20 : i how large the =argins are for licensing calculations, ne !
21 I l also have used this data to guide us in terms of identifying 22 '
- what areas need to be impreved frc
- the licensing kind of 23 ' 1 l
calculations to give us best-estimate capability. - This i 1
da ta , and particularly fu ture data , data that hasn't been 1 25 l available in the =odel develop =ent process, will be used for ALDERSON REPORTING COMPANY. INC.
~ .,
I l
l l
l ,
413 -
1 qualification of 3WR TRAC.
7-AS 17 i
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2 DR. CATTON: '// hen you take ycur EM calculations 3 like you have shown here, are you careful to include in i
4liI them the excessive wall heat transfer and things like thic?
i e ~
5! l DR. EURNITT2: Yes.
j 6l DR. CATTON: You know you are doing it'in a scund R
$- 7 way and could one of the reasons that there are big dif- -
- N j 8 ferences be effecta of scale not properly accounted for, J
d 9 too much metal heat transfer that is not accounted for i :
$ 10 ! =aybe completely? How do you know you have accounted for z t ;
= i j
11 it properly? Do you do heat balancea on the :etal and '
a !
j 12 so forth? ,
" i
_2 13 i DR. BURNETTE ' In the licensing comparisons, I i
=
j
. i don't do them. I haven't done that prograc, but they are 14 l l E 1
{x 15 rather thoroughly done and thoroughly docu=ented. For j 16 l example, these two figures I pulled out of a rather large !
- i g 17 ! document and those suecifico have been addrosced. H 3a -
y 18 i
{n loss difference is one of the ones ths: jucpa cut. Ihc b
- 19 non full-length scaling is another that 12 tr ea tod . So n 1 20 they are addressed. The thoroughness of how well or how i 21 properly they addressed, I have to not take a crecic a
22 I that.
l 23 ' LR. CATTON: I just get a nega ive feeling when 24 ' I 3ee EM calculations on a nontypical kind of facili;7 You 25i did not have a si=ula ted 3WR so I don 't knew what the IM h
. i l ALDERSON REPORTING COMPANY. INC.
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I s13 1; calculations mean. That la just a ec= cent, ycu don't need i
l 2, to answer. l 3 aR. BUR:GTTE: I would like to. What they mean !
!- 1 1
4l to ce is the licensing calculations when applied to hic e 5 TLTA with all its differences and cc=proaizes and so on, 9
3 o 6 is conservative. The next extrapolation to sav therefore R
8- 7 all reactor calculations or licensing calculations for 3WR's Q 8 are therefore conservative is a big extrapolation. I don't d
d 9; say that. I think it gives us a warm feelinz that they are i-1
@ 10 indeed conservative. Certainly I don't think even our x '
=
j 11 l licensing folks would say therefore our licensing calcula-a !
'f= 12l ,
tions have a thousand degrees of =argin.
- i
_s 13 l DR. CA2:0'I: Wha t would have happened if it were m , .
$ 14 i the other way? '
t i i E 15 ; LR BUR:GTT5: Inere would have been a lo of 5
i t
j 16 j excitement, j
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=
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i ALDERSON REPORTING COMPANY, INC.
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.i P41 1 DR. CATTON: And a lot of disclaimers.
/ \
2' ha. 3URNETTE: There are a lot of disclai=crs.
3 DR. CATTON: There wculd be a let cre, f
4 DR. ZUDAUS: Isn 't this , theu;;h, a pociti"a indi-e 5 cation that you can have a test to do EM calculations and n
n.
lg 6 they check very nicely? l
_- i N
$ 7l DR. CATTON: I'm net sure, but they did not check 2 8 a very nicely.
U
~-
z.
9! CHAIRMAN PLESSETT:. They purpertad to be vary C
5 10 z conservative.
=
~
4 11I DR. CATTON: That 's right.
3 12 E CHAIRMAN PLESSETT: Well, go ahead. These are O E U l3 13 philosophical ceteents at the eccent.
14 E MR. 3UR!iETTE: In terms of future direction cf ,
5:
^
15 m
=
the program we have a preposal en the table and have a
? 16 g separate presentatien to give on that, but the directicn is 17 3 to upgrade the facility and, hence, limiting all of its x l
. M 18 '
ncda scaling ecmpreciscs that are significant and run e:: peri-19 i j j ments in the area of more intermediate and small break cpera-20 !
ting transient si=ulation, including the effects of de-21 graded systems, cultiple failures, cperater interacticn, 22 these kinds of thi.gs, and also with the pcscibility of 23 ;
checking, of tas ting, advance reacter tfpe instrumentation, 24 >i l for a: camp 10, level instrumentatic.,
25 DR. CA! TON: Have feu dens a s7stematic scaling I
t ALDERSON REPORTING COMPANY, INC.
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study of the ILIA?
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6' l2 MR. 3UR:lET'2 : Would 7cu like xc?
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! MR BUR'iE'1""E : Ce rtainly , Under this propccal it d
9
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l is planned that there wculd be actually one-third ccep c-r 10 i j i hencive scaling evaluatien for this new geenetry, beca'ase
=
~
11 4 it would be qui::o different than the earlier rcrad.cco, a
i 12 ' DR. CAITO!: If 'rcu have that, I w uld like a
=.
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2
_ coPv of that ao tecil.
$ 14 a
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3 C;iAIRE:i FLES3ETT: 'de .;ill hear a' ut a discuc-z ,
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the constraints of the funding in :he :entract n:w a .d : hen 12 1 5 !
i pcssiblf a centract n:dificatien or new centract to de a
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g I chart that shews that the facilitf would be upgraded and a 1
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. w 18 In doing that we would 'a ' coking ahead tewards 19 1 8 t '. '. .c . eq u t _ '_= e .. *.a-n ; * . a '. a. . '. a- '.- ' o d o a d d ' ~. '- e ..a '. ~. ,~ees o' 20 '
cxperiments, the cperating transients a.d se en.
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- ALDERSON REPORTING COMPANY. INC.
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small site systcc.
2; We actsid like to run a zer d.as of ::mpleta ; cries O 3li fra: :cmpleta icwcut simulati:n ,f tic.e zar: ?. reficed 3
4l in a system that had full height acmpenent: :: we :culd g 5' reflood all the way up to the ::p ci the jetpemp;,
9 3 6; Thirdly this Phase I woull pro"ide the major R
=
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6 7ll facility =cdificatiens required to do cther experiments n .
8 Q such as operating transients, reactor instrumentation "J i 9l experiments,
.l g 10 l SPRI has claimed a name we have adepted for z
=
~
4 11 '! the acw facility, Full Integral System Test Facility er a 1 g 12 'l FI5T Facility. It w, quid have the capability, as indica-i
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13 i 5
tad by the objective, completa, integral cimulation I4 h for all sisc LOCAs, liquid breaks as wall as s team c_
7 15 l c
~
i creaks.
s I
f C
16 l We plan to go to full langth compenents and 17 d
=
, regions in all these areas, icwcr planum, jet purp; 5 18 u
! the full langth downeceer wculd allew us to operate at b
19
) the normal water level, wh!.ch is scTething we can 't new 20 i do, i
21 !
l Full length upper planum, steam separat:r, 22 '-
steam dcce and two other signift: ant changas in the l area Of bypass heat tra ns f e r , Right new in LIA, uc have a large atypically thick channel that is .ecessary 25 far the type of heater design we use, ~ hat thick channel l
- ALDERSON REPORTING COMPANY, INC.
I 119 i I
y s-w I with its therv.a1 insulater affectively biccks any heat is
\' l 2! tranafar from the cerc regica di.rectly tc the bypass i
3 regien, so that 4.3 an atypicality cf tha LTa we mi;Pt 4l e ?.iraina *.e .
I g 5i In this design we would use a pretotypical 2'ia a
+
g 6! channel so the bypass ceuld then also be rade just outside n ,
C
" 7* that channel.
. A-8 A Thia figure will give you a little of the per- -
ee i 9;
! spective of what the charge in length ia going to de. As z
=
h 10 ll Shcwn here, ILTA, the present TLTA pressure vessel has a I
= i Il
-3
, steam line ecmina cut here at the ten and then dcwn.
This E"
- 12 ! gives about the right aspect ratio, er rcughly correc t. )
\s-) l' 13 ll i The proposed facility ic much taller, as yet cee, i
U I 3 14j' a full height, full length typical ecnfiguraticn of the
= i i 9 15 s
=
steam line. Jet pumps would be mounted cut here in the 1
I i
l l T 16 ' l
'g side 1 cop with a couple of crossovers, jet pump fluid
- 17 l
d
=
i coming dcwn and across and up into the core regien, the 6
z 18 t g core region being right in here (indicating),
j 19 l' These are the highlights of hew the length 20 l
, scaling wculd be changed, i
21 i j 5cce of the other specifics, capabilities, 1 i
22 i '
again ist us de tr.terval er.periments, can inveke opera-23 ter intervention if we would like, All the ICC systems, 24 I
[~')\
's , : the safety relate valves, either separately cr in tandem 25 l
as in an ADS system, the operator and cpan or close.
I s
ALDERSON REPORTING COMPANY,INC.
I t
I
"-s l
p 5 1i We can do a much better icb on small break tests, l
2 the small break simulatien, the NILIA was at best rude.
t 3 The full langth in :cr=a ef--lets es :pera ta at ner a1 i
4' water levels so we ge: typical and natural racirculation
- 5 during the first part of the transient.
9 e
g 6 The refilling of the scale Orcss-sectional dern-n C
~
7j ccmer ac we would have in this facility culd be dene in j 8 !
real time, the level movecant could be done in real tice, d
9
$ i .whereas in TLTA, that volu=e was short and fat, so the
?
10 z 1 filline ra tes 4.n te rms of level covecent was not scale.
= :
!5 II l l In terms of LCCA simulatien, bcth large and g 12 l intermediate. breaks :an be done, Steam line breaks cnd
= I 3
5 13 i same limitatienc in this ar2a of encrating transients and m -
3 14
?_ natural circulatiens, kinds of e:: r eriments > primarily fr n b
~ i 5
x 15l' ;
the peint cf view that as presently secped, .'haae I wculi j 16 not have the haated feedwater system.
17 "d 3o it is still quita adequate for :any of these
=
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3
- 18 l kinds cf tects s tcarticularl" if ycu are simulatins the 6 i h
2 19 '
a licensin?o kinds of conditions where you icse - ::wer to vcur I
20
l statien and so on, sc you icse ycur feedwater.
21 l
- In sc=e of these other areas in cperating tran-22 '
jient si=ulation, the recirc-ficw changes , 22adwater ficw 23 changes, f eu want to have the capability and mecd the i
capability to inject feedwatar at the c:rrect to perature 25 l conditiens.
ALDERSON REPORTING COMPANY, INC.
l v.
1 tQ: 7 1 Some of the specific features of the core region j s ,
2i are a full size eight-by-eight bundle, as before; diract
{
3l 1 heaters, as beforc; but new a little variatien in the 4l spacer design.
1 3 5l Jith current passing thrcugh the skin of :he 0 1 i
@ 6 heaters the grid spacers beccee alactrically hot and, thus, R ~
$ 7 the need to insulate them in the configuration I dcceribed n
3
- 8. i before: with the insulater in the thick channel. .
J i 9 9: In this design, we directly insulate the spacars z '
c 1 g
z 10 l through a thin insulating material sprayed en the spacers
]a 11 and then the spacer would then be in direct c entac t , but y 12 l with the insulating material between them to the typical
- i 4 9 s/ j 13 i 3WR channel, m
z 14 5 The bypass would be rade concentric just outside G
j= 15 the channel. Typical 3WR geccetry at the inlet, the ficw j 16 l coming in through the vertical orifice, a so-called side A f t
l.I7
=
entry orifice, ccming up threugh the icwer fuel support y 18 i casting and typical icwer type plate, pretetypical or
- I g l9 ! actually typical of reactor hardware.
20
. The bundle cutlet would have the same, I guess 1
l l 21 + as indi:ated here, a fairly typical,not prototypic, in that '
I 22 ! the upper electrede needs te be thicker to carry the elac-23 '
trical current, so we can use a prcducticn type, upper type,
/ 24
( .
plate to raintain the fisw area geccetry but effec:ively 25 '
cake tha uppe r type plate thicker :o acce=cdate the cur-
- ALDERSON REPORTING COMPANY, INC.
1 1
1
\ ,r su nn
) I rent. The bypass inlet is prototypical with ene anception, 2 I guess. It has the reactor-like holas drt11ed for that 3l \
part of the leakage, but we can 't simulate the finger l
I 4! spring leakage direct 1;, so we aill augeent the drill I
n 5 holes to prcduce the same head ficw kinds cf charact2ris-9 4
5 6 tics to that leakage pack.
R I .
h' 7 The test plan is still in its icry formative s .
8 Q phase, then this is the kind of thinking that has been a
9
~. done to date, anticipating being able to run t2sts ever 10 g j a six-tenth paried, sc=ething like a dozen tests being
= i II 5 conducted in that period of time to fccus en small and a
d 12 m inter cdiata breaks.
- I
- 13 !
c We have planned one test without crerator inter-
~
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3 14 1 9
c ventien and one with. Acain, probab1v scce of the boil-9 15 2 l off kinds of tests that have been recentiv done and at
= ;
? 16 i 3 !
least one test in a large break docain so we can have a F
j 17 direct cceparison of the TLIA large break versus a FI3T E 18 '
_ large break iespense to try and get a eccparisen of
- E 19 l A l elminiating many of these scaler ccepremises, what that 20l has dcne for us.
21l The data utilization slide iceks very similar 22 to previous ones in terms of the best esticate models 23 and the =ain utilizaticn is evaluating the individual 24 ; physical =cdels within the everal pladicticn :apability, 25 The reo areas in utilizaticn licensing Ocdes i
ALDERSON REPORTING COMPANY, INC.
423 I
l' s is to assess acte of~these functicns that are nada and )
1l! l
\
2 then quantify the overall cargins that e::ia t , a ain 1 1
3I wnen applied to the e::perimental rata.
4 3chedule-wise, we are d.n a little trouble al-e 5 j ready. We anticipated starting the modification at the 9 i j 6l beginning of this year and the start hasn't occurred yet,
~
, 7l but 02.m. ica11v a period of 15 to 13 cenths of deaign
. n ,
5 8l fabrication, installaticn and shakedown and you see the J
9 9I activities brcken cut here, but typically 13 cenths to z ,
h 10 l get the facility, the modified facility, in a position z i
=
II 5 to run expericents. Then there is roughly a six-centh a
- g. 12 testing period to run these experi=ents, the kinds of (r~~ = I
\ g 13 i caperiments we talked about at the previous icvel, z
I4 DR. CAITON:
@ When it is all dene, who owns b
j
=
15 the facility?
g 16 MR. 3URNETTE: When it is all dene, the facility s '
17
(- is cwned by.the three sponsors in accordance with their 18 I
f respective shares.
8 n 19 ll i DR. CATION: They aach go in and cut cut a piece ?
20ll MR. 3URNE M : It is lihe a cendominiuc, "o 21 aingle place belcngs to anybody, but they all cwn a aharc 22 of everything, 23 'I Turning a little bit new trwards a felicw-ener 7hasa II . capability, you see the sace '<.inds of things here 25 with the addition of heat water s-stec and a 110:12 acre l ALDERSON REF' ' '
' P ANY. INC.
?
mprehensive cent cl syste and se on. 'de can go into 2 feedwater transient ;iculations, Icek at r.any of the 3 cperating transients , particularly a.s the; affect the l 4l ,
I level movement and the exarplas here listad are turbine g 5 trip, pressure regulater failure.
n N l s; \
$ i We can icek au recirculacien transients, step l m t l M
$ 7 incrcases, step decreases, pcssibly single icep cperations.
j ; -
$ 8 We can run with the full height simulatien and with heated J"
- 9 feedwater systet we can get--and using the characteristics z.
e 1 10 1 y" of the rate itself, we can get a handle en the ability to j II h calculate natural circulation.
- l 12 E There is a pessibility, also, by pre-prograrming ci 13 l the pcwcr cycle cf iceking at the cendition cf relativol-f 1
3 14 i g low flow and 20 to 30 per cent pcwer rang;e dcwn in the !
a:
jx 15 element cycle operaticn conditien, 3etting into the stabili-5 16 1 g :
, t~.r area.
I ,
"" 17 i i d That concludes my presentatien en that.
=
5 18 g
CHAIRMAN PLESSETT: Thank '?cu. .
Harold, do vou 19 ! I 8 ! think yce can conclude ,vour part in half an hcur? I n ,
20 DR. SL'LLIVAN : No, it is just a few minutes. )
21 C'dAIRMAN PLESSEI~: Fine, then ycu cc=plete ycur l
22 l part cf the 3WR pregram and we will have lunch and then 23 ' I cccc back for the staac e::plosien.
24 DR. St.LLI7AN: I think ycu indicated that all 25 tasting has been cocpleted in the current TLTA facility, I
ALDERSON REPORTING COMPANY. INC.
.. i
.+ 5 i g-'g 1 that the test series conducted was a large breah LCCA l
(_ / 2 scrics, a anall break LCCA with and wthcut the single 3
failura, a bcil-off series and the facility upgrade is 4
under eval':ation.
I e 5 j The results from the large break series talls 8 i
$' 6I es there is a significant spray cooling during the bicw-
- M
" 7
- dcwn period. dhR has requested that we lock at the heat U
M 8 transfer coefficients during this peried of time under J
~ 9l E
i the LOCA conditiens.
10 '
j A significant point here is that we have re-
=
5 11 g pcated the two tests that cause us to go to a board noti-
'2
,_s E
ficatien and that is the with and withcut the ECC. We
( 3 13 i s put in additional instrumentatien tc lock at the break ficw E 14 '
d and we hcpe we have enough data to enter that beard noti-e 9 15 g
ficatien before we ter=inate this test series.
~
16 3
m Je rr.7 has alreadv. noted the ne::t item and the F
jc 17
.eports are due en March, of 1981.
z 18 l
- l The small break, the pr2-aralysis has been dene 19 l j j and they indicated there were significant deficiencias 20 and the ACRS also noted that was the case. This was trans-21 nitted te ~dRR. They were also aware of the prcblacs we s 22 were going to have'when we started this snall br ak series.
23 '
, The--as in the 7LEC:i! program 3 there is a prcgram 24 i i to cenitor the ILIA program in Idaho. They did a blind 25 ,
predicti:n of the small break tests and that was a request ALDERSON REPORTING COMPANY,INC.
.a 44.
l 1! !
from NRR. The small break and the boiloff reports are due l I
2; in January cf 1981 as a graph and the I"EL cal:ulations l l
3{ and the cetparisons today and sc=e repeat calculaticas, ara l
4l due in May of 1981.
D 5: ;
The single heated--thase are the requirecents j 6, for this new facility as we saw them, as research saw them.
G i : -
o
- S 7 We have had meetings with SRR and also with severalother A >
j 8' interested parties and pecple that were kncwledgable in the e
9 BWR area such as Lahey.
E 10
- g The requirements we cace up with, that we fcit ;
II s
- wa needed a single bundle test facility. We couldn't find 12 s ! anybody that would stand up and say there was a problez ;
= l j
13 ' '
with, that wculd require a culti-bundle test facility. l 3 14 I The thing we did find was that pecple said there might be l 2 i ,
e i ,
9 15 g
a problem.
i 16 g'
We were trying to investigate scrething that say l
y" 17 .
be in the future.
i 5 18 i l The ROSA III facility showed no unusual nditi-
" l j 19
- channel effects. We have icoked at that data to help us ;
f 20 qualify the statement that we need a single-bundla faci- '
21l lity.
22 '
We believe the vessel needed significant upgrade 23 l and cne of the significant point; is the height of the jet 24
- purp. We are unable to perferm a lot of the transients, 25 as Jerry indicated, so we Selieve we need a full scale i
ALDERSON REPORT!NG COMPANY,!NC. :
i
,/ .0 9 1
I height in that area. '
.!(s,- 2 We also think the suppcrt facility, in particular l 5- the instrumentatien and centrol, need to be upgraded, have i
4j .
a significant upgrade and we wculd be locking for a very l
e 9
5i goed transient simulation.
a
$ 6 Also we think we cusht to investigate anr '
methed n
e
" 7 .
we can to lock at the pcwer. void feedback. We just can 't
~
s 8
$ get it in an electrically heated facility, but we would a
9
~. try' to simulate it.
?
E 10 g We have two propesals that we are currently lock-
=
II 5
a ing at and cne of them is frco G.E. The cost tc NRC is d
2 12 l abcut 2.2 21111cn dellars and we would be getting data
/~'T $ 13
(;,/ g ,
in FY-82 and FY-84.
3 14 2 DR. CATTON: When you have a single bundle faci-u 9 15 g lity, len't you have to centrol the beundry conditions at ,
16 g"
both ends of that bundle to average core conditions?
" 17 s Then if ycu want, particularly, to 1cok at the E 18 g hotter bundle at a high pcwer regien, you wculd have to t 19 A control the boundry conditions to average core conditions 20 i when you do that.
21 DR. SUL._; VAN: Yce wculd be restricted to aver-22 l age power, 1
23 !
DR. CATTON: So if ycu have a single bundle all fN 24 l ycu can 1cck at is average pcwer tfpe conditi:ns?
l
(
25l l DR. SULLIVAU: The types of tests we arc going i
! ALDERSON REPORTING COMPANY. INC.
- ..,, . - - . ~ - ,
1 l
i' i 4 o 4.e3 i
I j to lock at are going to be where ycu would like to 1cck at i 2i an average :cre. There are thinge like operational tran- i i
3l 31ents. '.'cu wculd ha locking at tbe whc12 entire plant, 4l not 4ust in terms of a h'.2h c.ower bund 12. w ,
i 5
3 i DR. '4U: Harold, '.cw abcut the .atural circula-v )
i 3 6 i e '
tien criteria 9 -
R .
l
? 7 ~I d DR. 5ULLI"AN: I think ycu have to have a let of i 8 M
'J i bundles be" ore veu would be able to icek at the natural j
9l '
}"
- circulatien. i i
l 3" 10 l DR. CATTGU: Or at least ene hot and Ona cold.
5 11 !
g ! DR. SULLIVAN: At leact.
'i 12 5 DR. JU: Well--
13 i E
DR. SULLIVAN: I would doubt that wculd reall,,-
$ 14 '
s= i give "ou an adequats--the second prepccal was frc a r 15 l: l I
i national laboratory which was Idaho and the number, there
~
16 l
$ ; is a mistaka. The single bundle facility was about $10, F 17 d
=
\
000,000 and the multi-bundle went higher.
w i z 18 i i
I The data is a let later, c: what ne are icekin;
- 19 A ! at is the relative cost to NRC and it is a lot lacs by i 20l l 3cing to G.E. and we wculd be able to ;ct data. There ara ,
21 i l l also disadvantages. One wculd be in tars: of the ratic.a1 >
22 l ;
labs .chace no weuld Saue a lot :re c:ntrol cvar the :: - .
i 23 ' i a~.^' a..' q u ac.'.'.' " ~. .~ ".." o ' ... "...a.. '
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25 I DR. CA TON: '4 hat would ,:u de w_th d
- no-thire :S !
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, ALDERSON REPORTING COMPANY, INC. I
i
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I p a faed. lit when 3.t is :"c:?
2' DR. 3CLLI7A.i: As far as I ' . : -c arr.el, t'c 2 3
facilit; bel:ngs to G.2, Wa huve no plan: i:: c':: :r e-4
- u. %. 4. . A .m 2 2 ~. .
5
$ DR. TH20FX?CU3 : Is there any other facility v
g 6i in the world that is usin e Pa:allel side effects ?
4 7 -
i.k DR. SULLIVXI: Dr. 21essett '.as made ::s aware,
~
8!
T' d
or at least mere aware, of a facility that is in Japan d 9 g
I which is also full height and is a two-bundle facility.
E 10 E
We are currently locking inte : Fat, anploring h the possibility of beinginvolved in that program, also, c' 12 rs 3
- DR. THEOFXiCU3 : This facilit .r is a linear f : 13 '
i facilit; through all phases of the accidants, this opera-E 14 W d
'w..n.al "acd"-?
e
< 15 j DR. SULLI7AN: We are just nct that far.iliar
- 16 g with what they have done or tried. We underr,tand it vac 6 17 g
w a large break LOCA facility and that was t!.e main purpese,
. z 18 2
s You can take it and extend it into other regicas and that
- 19 A is scmething we need to find out and we are pursuing that 20 ,
3CU.
21
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22 Se back pr:mptly within an hcur.
l We will hare cur discus-23 ,
si:n of steam explosion work and go back :: the f'nal m2t- )
24 ;
\ tar.
25 .
So, let us try to be back at 1:40 c: ic. One hcur.
f ALDERSON REPORTING COMPANY, INC.
.~... _ -- . _ _ _ _ _ _ _ _ . . _ .
l 430 l ,
('Jhercupon, at 12:40 0 8:1 ch p.m., the =ce'1.g i
2' 8 wu adjourned to recenvene at 1:'O 2 clock p. .., :he 3;
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431
- ^il PV I AFTERNCON SESSION 2
1:40 p.m.
3 CHAIRMAN PLESSETT: Let us reconvene. )
4 We are going to have some discussion on steam ex-I 5 plosion.
y n
.j 6l Mr. Sherry, are you going to start?
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= -
" 7 MR. SHERRY: Yes.
A S 8 M STATEMENT OF RICHARD SHERRY, d
~ 9 j U. S. STEAM EXPLOSION RESEARCH, F 10 j OVERVIEW
=
E 11 g MR. SHERRY: My name is Richard Sherry.
c 12 g I am going to be presenting an overview of the s 2 13 g program.
E 14 y
Then Mike Corradini, the Saadia task force leader
-0 15 j
- of the explosion program,will be making a presentation on 16 3 t he details of the experimental, analytical program.
H 17 i
@ l The other main contributors to the steam erplosion
. E 18 g program are Dr. Ber=an, who is the program manager at Sandia I 19 A for the core melt programs; Dennis Mitchell, who is the lead 20 investigator on the large scale fully instrumented test ser-21 ,
ies facility, and Lloyd Nelsen, who is the lead investigator 22 on the small scale single droplet test.
23 '
My part of the presentation will be fairly brief.
[ 24j
( 25
- In my part of the presentation, I will be presenting an over-i view of the steam, explosion phenomena, its significance to l
l ALDERSON REPORTING COMPANY, INC.
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i risk and to reactor safety.
2i I will review the containment failure, a probabil-i 3' 'ty estimate, that which was calculated with reactor safaty 4' studies.
i s Si I will also go over some of the alements of our 9
3 6 NRC research program at Sandia. I will present a very brief R
$ 7' summary of the most important results, to date, from this
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s j 8 j program.
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9l t I will present, additionally, a new set of risk c
l= 10 l estimates which have been developed by Sandia just recently.
The presentation which Mike Corradini, then, will fII 12 E" l present to you, he will describe the experimental ,rrograms 13 at Sandia and will describe the model development activities z
I4 l= and the analytical studies where we have been.
F g 15 l Mike Corradini will previde also some additional
' i j 16 r l
details on the new set of risk estimates.
" 17 '
d This slide (indicating) presents a very brief en-
=
g 18ll planation of what a steam explosion is and the procasses '
19 i j that are involved in a steam explosion, in a light water 20
, reactor.
21 L A steam explosion is a rapid and violent heat r .
22 i I j transfer event which can potentially occur when a cool i 23 l I liquid ccmes in centact with a hot liquid whose tamperature is well above the boiling point of the cooler liquid. h 25 l
! The sequence of 2 vents which we believe will occur l i l l l , ALDERSON REPORTING COMPANY, INC.
l
433 l 1 can potentially occur during a melt down accident is that ,
l 2 a large amount of molten core material centact, residual 3 coolant water either in the lower reactor vessel er in the 4 reactor cavity following the vessel failure.
j g 5 In order for a steam explosion to occur, we be-S j 6 lieve that it is necessary for this glob of molten material E ~
7 3 to break up into smaller motien particles on the order or
. 6
] 8 one centimeter in size and mix with the residual coolane.
d 9
}
During this sta2e of the process, a steam film E 10 i will develop around the fragments and a period of somewhat E 11 j stable film boiling will exist.
'i 12 E Some local event such as a pressure vent will 2 cause fine fragmentation in the local region of the .:1.:turc 1
E 14 '
y of molten droplets and coolant.
F 15 j
- This fragmentation results in a large increase in 16
$ surface heat transfer of surface area which allous rapid i 17 g i boiling of the coolant and local hard pressurination.
5 18 g This region of local high pressure then causes
$ 19 {
a a pressure wave to move through the mixture initiating ad-20 dicional fragmentation.
21 This propagates the shock wave. Following the 22 propagation through the mixture, taa entire mixture is in a
- high pressure being constrained b'f surrounding materials.
24 l
\ It exceptionally expands and may do damaging work 25 against the =ajor constraints such as a reactor vessel. >
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! ALDERSON REPORTING COMPANY, INC.
l 434 I
i I
'G. L!ENHARD : Do you have a mechanism for break 2l i up in there? I notice that you do not mention lccal pras-3l! suriestion until you get two items further dess.
4 MR. SHERRY: Under this phase, it is the brsak up
$. of a large mass to particles on the order of one to two centi-3 6 1 meters in size.
e n
. 7l? We of ten refer to it as a pre-frag =entation. .
8 8l a MR. LIENHARD: I have been studying the Sandia
- 9' g
, movies lately. It appears that the break up occurs as the n 10 i E i' result of terrific impact on the collapse of the first blank-5 11
$ eting. .
12 j# l MR. SHERRY: There are two fragmentation events s 13 !
E , which we are discussing which we believed to have occurred.
$ 14 I u -
y ! The first is an initial pre-fragmentation down to 2 15 s ! the large mass to smaller particles in the order of one,to e 16l A
two centimeters due to perhaps boiling forces.
f 17 '
s ! A steam explosion, a rapid heat transfer, a rapid M 18 '
E steam production sufficient to cause local pressurization t* 19ll
= 1 1 will not occur during this stage.
20 l What is necessary is to break up these droplets into' finer particles, MR. LIENHARD: That is latar.
23 MR SHERRY: That is :he later stage, yes.
25 .;
I MR. LIENHARD: So you are talking about perhaps e
i l
ALDERSON REPORTING COMPANY. INC.
433
T I a break up of a molten jet or perhaps something of that 2 30;;7 3
MR. SHERRY: Along the later stages, we believe 4 that what exists are then the small droplets surrcunded by a e
g S
vapor film and then some local event such as a pressuriza-3 6!
- ! tion collapses film and initiates a fine fragmentation.
. n n 7
- This is what occurs. The reasons we are concerned e M i 8
" for here the steam explosion phenomena in the reactor safety l
6 9 j area are because of the following points:
E 10 E
The high pressures which are generated during the E 11 s propagating and steam explosion may directly fail the react-d 12 fs 5 or vessel or the rapid production of steam could result in I 5 13 !
\' E j direct over pressure, failure of reactor systams or reactor E 14 cooling system proponents such as the steam generator.
2 15 s The mechanism which is of most concern is during j 16 A the expansion phase when it is possible to accelerate ma-y 17 i E terials that surround the interaction region against the u
z 18 5 reactor vessel, such as, if he would have an interaction of t 19 A ! the lower reactor vessel, one could accelerate an overlined 20 !
slug of the core materials and water against the upper react-21 or head causing the upper reactor head to fail and potential-22 l ly generate a missle which could threaten the integrity of 23 the containment. ;
% 24 j 3
[\ ' The violent forces which occur due to steam ex-25 plosions or which any be possible because of steam explosions l ALDERSON REPORTING COMPANY, INC, 1
i i3 1 may impart gross motions to the reactor vessel and these 2 vibrations or these motions are transmitted through the re-i !
3i actor's coolant system through the centainment, and you may 4 possibly then result in, containment penetration.
s 5 It appears that it would be also possible to dam-
- l 3 6 age containment emergency safety systems such as contain-R -
$ 7, ment spaces which wou.1d generate a missle on the part of the-j 8 reactor vessel.
'J i L 9i DR. ZUDANS: You previcusly heard them talk about
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@ 10f what can happen inside of the reactor vessel.
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MR. SHERRY: Yes. I am going to be concentrating l j 12 i on my discussion cf the steam explosions which occur within l
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the reactor vessel.
% I4 l As I did indicate previously, they can potential-E !
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15 ly exist. Also when the molten core fails the vessel, melts j 16 through, it can contact any water that may be in the vessel A
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3 DR. ZUDANS: In my mind is how =uch time is there c
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between the point that you have just described and the time n
20 I the molten core will go through the bottom of the vessel?
21 I l MR. SHERRY: Perhaps I don 't understand. The time f
22 the molten core will collapse :hrough the reactor core cav-i 23 ity?
DR. ZUDAMS: Just go through the bottom of the 1 25 i reactor vessel.
1 ALDERSON REPORTING COMPANY, INC.
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(h CHAIRMAN PLESSETT: That will take some time. You 2
still have the possibility that he is considering falling 3
into the pool of water within the vessel.
4
! DR. ZUDANS: And that would cause the damage to I
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i the vessel?
3
- 6 CHAIRMAN PLESSETT: That is what he is looking at
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- i now, causing steam explosions within the reactor, the reactor
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g j DR. ZUDANS: All right. I do not know where then E 10 -
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l 2 11 s CHAIRMAN PLESSETT: I don 't either, but let us d 12 i j speculate.
'd MR. WARD: Maybe you will get to this, but is the
$ 14 I
$ ! scenario,that molten core melting into the pool of water 5 15 i s l at the bottom or is it that molten pool of core being hit J 16 i G ! with water, or does it make any difference? Which is bet-17 ;
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s ter then?
. $ 18 5 DR. CATTON: I think what is happening is you are t 19 A melting the core down under the force of the place and that 20 fails and drops into the water that is in the lower plenum.
!i CHAIREMT PLESSETT: You are assuming that you 22 1 l
have water in the lower plenum?
23 DR. CATTON: That is right. The question is p 24 l
( whether or not they are going to have a staam explosion.and 25 damage as a result of that. This gives a limited amount of i
i ALDERSON REPORTING COMPANY, INC.
f 433 I water to replicate.
2i MR. 3HERRY: Yes, between ten and thirty metric 3, tons.
4 These, in 1973 and 1974, it was part of the react-i g 5 or 's safety study analycis. The analysis was performed to a
j 6 try to indicate the risk of the containment failures with n*
y 7l steam explosion events.
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2 M 8' In the analysis performed for the reactor safety a
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$ 10( credible mechanism for failing centainment involved, the 2 !
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melting of a large mass of molten core and then this mass of 0 12 g l molten =aterials, approximately 20 per cent of the molten 13 '
core or greater, falling into the lower reactor vessel and s
E d 14 l contacting water in the lower reactor vessel head.
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2 15l A steam explosion then occurs, accelerating an E
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$ overlying slug of material and gives the upper reactor ves-d 17 sel head or hits the upper reactor vessel head with suffi-g ,
$ 18 l 5
cient force to cause failure of the upper vessel head be- -
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$ 19 l l a l low the flange.
20 l l !
Then to accelerate this missle, which was the 1
21 !
! upper vessel head, against the containment would be the 22 i next thing.
23 To quantify this esti= ate, they developed this 24 three factor equation where ? Alpha is the probability of 25 a steam explosion, a failing contain=ent during a premelt ALDERSON REPORTING COMPANY, INC.
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down accident.
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-- 2' PFCC is the probability that a large mass of molten 3
core materials, greater than 20 per cent o f the core would 4 contact water during that melt-down accident.
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PF is the probability that if a large amount of n
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i which would fail the containment as a result of mechanism I described, fII e 12 This takes me back.a few years z CHAIRMAN FLESSETT:
('N) 4 6
Nd i 13 to where we were talking about fast breeder. There you E 14 ' have a lot more energy to talk about and you really are d
e F 15 9
concerned about the possibility of lif ting the head and
.- 16 s i making a missle out of it.
d 17 i You do not have that kind of energy here. I g l
$ la i wonder how you got off on this frankly.
5 I 19l.
i A ! MR. SHERRY: There is certainly enough energy in 20 the molten core =aterials.
21
[ CHAIRE\N FLESSETT: 3ut nothing like a breeder.
22 I I Even there now, a lot of people don 't believe that you i
23 could even have this kind of event with a breeder. l I
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If you think this could happen seriously--
25 J There is certainly enough energy in i MR. SHERRY:
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2i CHAIRMAN PLESSETT: That is not my point. though.
l 3 ,l There is a lot of energy, but not as ruch as a braeder uhi:h i 4i 3ces recritical. Even there there is a question about g 5 whether you could lift the head off of the vessal, 9
3 6 MR. 3ERMAN: There ar2 two factors involved. One a i .
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is the energy available and the other would be. the components a +
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c , That is exactly what we looked at that that point.
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y' CHAIRMAN PLESSETT: If you are going to do that
" 17 d .
without much question, you could get a lot of dama'ge, but
= i M 18 +
g the big question about that I should think, what is your j 19 feeling? Let us ask Catton.
20 DR. CATTON: Do you mean with respect to the steam 21 explosion penetration of the upper head?
22 "
CHAI2 MAN PLESSETT: In making a missia out of it.
23 DR. CATTON: It is my understanding that the r2-suits of the Sandia program had sort of demonstratad that f 25 j i that was not going to happen.
1 ALDERSON REPORTING COMPANY, INC.
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("g Il CHAIR'3.AM ?LESSEU: That is right.
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DR. CATTCM: It is not going to happen in the ';ay 3'; that would lead us into trouble because of the way that the l
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$ f You would not hurl the head as a missle, but there i 12 !
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$ ! nature, and that is, what does the stuff look like after 2 15 l
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j 16l You are talking about what w : CHAIRMAN PLESSETT:
i 17 y happens later en?
. 5 18 E DR. CATTOM: That is right.
0= 19 l i a i CHAIRMAN PLESSETT: Which is more to the point.
20 l DR. CATTON: Although the explosion may not cause a lot of damage, the fact that there is an a:cplosion leads i
22 '
! you to a different pile of rubble than if ycu did not have 23 '
it.
24 1 i
CHAIRMAN PLESSETT: I agree with that.
DR. CATTON: All of these things come into play.
i ALDERSON REPORTING COMPANY. INC.
1 I _ _ __ _ _ . _ -_ . - _ , - .- . . , - . -
i 542 s 1l CHAIRMAN PLESSETT: The interest in this nart of l
l 2 the event, the possibility of melting cors interaction with l
3l uater within the vessel, but as to what you get afterwards, 4I I don 't think that it is going to do anything of 2ny real e 5 significance compared with that which is going to follow A
j 6' this when it melts down to the bottom of the vessel.
R 5 7i DR. CATTON: The author of the Sandia study is
- 7. .
i 8 A here.
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9 MR SHERRY: We will get to these questions.
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C 10 i CHAIRMAN PLESSETT: We are trying to sive a little
? 11 l tLme.
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E : DR. CATTON: What we are trying to do is get past
- I
- 13 i You cannot convince us that you are go-
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s your introduction.
$ 14 I d l ing to unzip the head and make a missle cu: of it.
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MR. SHERRY: I think I will go through my notes.
16
$ : CHAIRMAN PLESSETT: Let us skip that. We will i
H 17
@ ; accept that that did not happen.
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g l You might correct it and you might get some frag-0 19 '
4 .
=entation within the vessel and so on.
20 ,
MR. SIERRY: I will act right to the numbers then.
21 ! '
CHAI2 MAN PLESSETT: Good.
22 l MR. SHERRY: 3riefly these are the estimates
]
which were developed for the reactor safety standard.
) ihe bottom line was that ther2 was one : hance in 25 l ene hundred of fai'.ing as a result of this steam e::plosion.
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ALDERSON REPORTING COMPANY, INC.
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[ Il That was the estimate which we had done with the 2'
reactor safety study.
3 i DR. ZUDAUS: Is this an absolu::e probability of f
4 a condition?
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MR. SPIRRY: This is an absolute probability, k6 g
i This is your conditional probability.
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- DR. ZUDANS
- Are you telling me that every reactor
. ei 2 8-6
, out of one hundred will have a steam e:cplosion, if it is an a r
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- g. MR WARD: We are getting at core meltdowns.
l 2 11 s DR. ZUDAUS: That is a big condition.
4 12 l j j MR. SIERRY: That is what I said.
d 13 S CHAIR;!AM IPLESSETT: Assuming you have a core =elt.
$ 14 ! i y ! MR. SHERRY: That is what I said.
2 15 ,
5 i DR. ZUDAMS: I ask you, is that conditional or ab-j 16 ! l A ! Solute * '
f 17 s DR. CATTON: It is conditional. Ycu have to have
$ 18 5 a certain amount or more than some amount of the core molt.
'n' 19 l a i CHAIRMAN PLESSETT: So it hits the water?
20 f DR. CAITON: So it hits the water.
21 l MR. SHERRY: Those are included in the other terms.
' 22 ,
i I am just giving you the bottom line.
23 DR. CA~ ION: That is not really the bottom line, 1#
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as the bottom line has to include the conversion of this.
25 I think you have fcund that the conversico efficiency is such ALDERSON REPORTING COMPANY,INC.
l 444 I '.e s s .
2l MR. SHERRY: I am just presenting what the NASH 3l 1300 results were. I am soing to get into :hst our new es-4l; t imates our.
I y 5l CHAIRMAN PLESSETT: We were villing to let you skip
?1 3
n 6l that.
n 7 j MR. SHERRY: I just want represent a base line e4 i 8 M
e and this is a measure of the impcrtance of steam explosion,
- 9 g
- i containment, failure that is relevant to the others with s 10 '
i the WASH 1400 PWR.
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- j These are the containment failure modes. All e 12 y of the =olten importance for the containment failure modes
- 1, i ; for the referenced PUR in the reactor safety study are i 14 i
$_ here (indicating).
E 15 y I just want to show on this slide that even using
? 16 i
$ the reactor safety study estimates the importance of the i 17 :
y ; steam explosion containment failure modes to core meltdow -
5 18 I E risk are marginal, on the order of two or three per cent.
I 19 '
A Now I will get right to the new astimates.
20 CHAIRMAN PLESSETT: That is good.
21 1 MR. SHERRY: Within the last three months Sandia 12 ;
has sent a draft report to the NRC where they sum-nrize the 23 l erperimental and analytical program.
24 :
j Also, based on these research results, over the 25 g J past several years, they developed new quantiative esticates l 1 l l ALDERSON REPORTING COMPANY, INC. l l
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445 l
LA 1! for the containment failure probability on the core meltdown l
(s'- ') 21 accidents due to steam explosions.
3 Quickly, the probability of contacting a large 4 amount of molten fuel with residual coolant is still assigned i
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the probability of one; the probability of getting a frag-
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12 1 "5 l Overall, the best estimate probability of failing
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as the result of a secam explosion during core meltdeun ac-s 14 !
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i cidents is a factor of one hundred less than the reactor 9 15 '
- l safety study estimate.
i 16
$ j DR. CATTON: You have an upper boundary of point jF 17 zero one?
M 18 l
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l MR. SHERRY: Yes.
l E 19 !
4 l DR. CATION: Where do the Sandia and LASL studies 20 l
! fit into this? Shouldn 't that change the probability of 21 !
l generating that missle? The LASL study seemed to indicate 22 l
! that the failure would not be ripping off the head?
23 MR. SHERRY: Yes.
/~' 24 4
( 25 I DR. CATTON: If the failure doesa 't significantly i l
, i
.i rip off the head, doesnit that change this?
I i ALDERSON REPORTING COMPANY, INC.
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I MR. SHERRY: These estimates might even go, rather, 2
can go into details as to how these esticates were gener-3; ated, but Mike Corradini can certainly e:: plain the details i
4 better than I.
j 5 MR. 3ERMAM: May I speak?
6 CHAIRMAM PLESSET"': Are you going to make a pre-
= -
E 7 sentation?
a -
- 8 M !
MR. BERMAN: Mo. I just want to perhaps answer a i a 9l g l Ivan 's question.
I: 10 i g CHAIRMAN PLESSETT: Would you identify yourself.
7 11 l g j MR. BERMAN: Mr. 3erman. These data do include 12 l '
! the recent works of Sandia in Los Angeles. The best esti-E 13 5 cate result is now 100 times lower in ',l ASH 1400, or the up-
$ 14 !
per bound happens to coincide with the UASH 1400 results.
9 15 l OR. CATTON: If you are doing a licansing assessment 16
$ i you are stuck with the upper bound?
H
. 17 ! ~
g MR. SEERRY: The upper bound is a very very con-5 18 5 servat!.ve bound. It dras.s an assucption that 40 per cent of I 19 A ,
the cores are involved in interaction and you are using es-20 sentially Mezies type of energy in the first ratio.
! DR. CATION: So it is not nonsense?
22 <
MR. SHERRY: It is the upper bound.
23 MR. BFRIAN: If you look at the WASH 1400 study--
24
, CHAIRMAN PLESSETT: That would be sure to make it 25l '
o ther than point ::ero one.
I ALDERSON REPORTING COMPANY. INC.
l 447 L 1 DR. CATTON: I think your upper bound is coo high.
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MR.. SHERRY: The components of the term which has 3, changed most dramatically the probability is steam explosion, i
4l the intial probability.
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These are shown on this slide (indicating). The g 6 important term, which we used in developing this estimate, E i C 7 is the term "P Slug'l, which is the probability that you will -
8' J
generate a slugging material with sufficient energy to fail h9 I
the reactor vessel which means that you have to generaf:e 10
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that with energy of approximately 300 megajouels.
2 g 11l As part of this program,..we have also done a d 12 i structural analysis of the way the reactor vessel would re-5 spond to steam explosion generating loads.
E 14 '
= As Dr. Catton indicated the analysis indicates 9 15 ,
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t that the failure mode of the reactor vessel appears to be 16 ,
- y. not what was considered in the reactor safety study, the l
~ d 17 g , circumferential rip around the vessel at the flange, but E 18 l 3 l more of a cracking in the upper dome, and a splitting of I 19 A i the head.
20 !
j Consequently, it does not look probable that you 21 '
l would generate a large mass missle even if you fail the re-22 actor vessel.
23 i That measure resulted in the assignment of these two terms "PDf' and "PSM", where PDI is the probability that 25 you would generate a large missle, a large mass missle of ALDERSON REPORTING COMPANY, INC.
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1! many cons from the recctor vessel.
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2j If you load the reactor vessel with a slug of I I 3:
I material greater than 300 megajouels of energy, . that is 4i true, and similarly, the PSM is the probability that you e 5j will generate a small mass missle such as a control rod
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@ 6' drive assembly with sufficient energy to fail the contain-E 5 7l ment structure.
5 g 8ll These have both been assigned the probability of d !
d 9 ten to the minus two.
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10 CHAIRMAN PLESSETT: How do you lift this slug of k
u Il material?
g 12 l MR. SHERRY: The slug of material simply are the a i 13 l3 initial constraints around the reactor lifter which are 14 i j l molten core droplets in water.
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! CHAIRMAN PLESSETT: But they are now at the bottom I
T y 16l! of the vessel, right?
a j7 ' .
d MR. SHERRY: Yes.
m G 18 l
= I CHAIRMAN PLESSETT: You are going to let some slug 5
19
$ l through the top of the vessel?
20 !
i MR. SHERRY: Yes.
21 !
CHAIRMAN PLESSETT: How are you going to do it?
22 j i What is going to lift it?
23 ,
MR. SHERRY: The molten materials which have ,
dropped into the low reactor vessel mix with the water. You 25 have material which is surrounding the mixture.
ALDERSON REPORTING COMPANY, INC.
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j A:49 L9 1 . CHAIRMAN PLESSETT: Which is water.
/ T l 2 MR. SHERRY: Which is water and also maybe the 3l mixture, itself, and they also have molten core materials 4 and structural components above that.
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CHAIRMAN PLESSETT: What is going to drive it up N
@ 6l through the top?
F E 7l MR. SHERRY: You have a steam explosion event. -
. r g 8 CHAIRMAN PLESSETT: You say steam explosion, so, J
$ 9 all right, I get a shock.
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i, 10 FR. SHERRY: You get a shock.
= l 5 II ' CHAIRMAN PLESSETT: Then that shock is going to is g 12 life a significant mass of material?
Os 5 !
- (j j 13 i MR , SH ERRY: 'The shock is not.
m
$ I# f CHAIRMAN PLESSETT: What is it using? What is k i F 15 '
g lifting it?
?
16 I Behind the shock wave, there is frag-3 MR. SHERRY:
l
' 17 d ,
mentation, rapid boiling, pressurization which is driving
=
5 18 After the shock wave is past, you still j the shock wave.
t 19 '
A ! have this high pressure region which has been constrained 1
20 :
by the materials.
21 CHAIRMAN PLESSETT: What kind of gas?
22 !
l MR. SHERRY: High pressure steam probably.
23 '
CHAIRMAN PLESSETT: It is going to lift this?
! 9 24 <
j MR. SHERRY: It is just going to expand.
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! CHAIRMAN PLESSETT: How much velocity can you get
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out of it lifting a slug of liquid with a gas?
2' MR. SHERRY: I think the estimate is somewhere 1
3 between two hundred and six hundred per second.
4!
CHAIRMAN PLESSETT: You are not going to be able j 5 to drive that.
j 6' DR. ZUDANS: Mr. Chairman, this missle is not G
h7 3
the slug of material, bu:: this missle is a piece of the ,
n 8 O
i head or a rod due to the pressure.
t c 9 g-DR. CATTON: After the impact, would the head I- 10 i i-then create'the missle?
Ui 11 g DR. ZUDANS: I could concede that if you build 12 '
g up pressure sudden l y , you could rip the head off or a 5 13 i piece of it, or you could extrude one of the control head
$ 14 i g ; drives and lift it, theoretically now.
E 15 !
s l CHAIRMAN PLESSETT: Theoretically, you could do 16 i
? . a lot.
F 17 *
-- 1' DR. CATTON: I think that you make the assump-5 la !
5 tion, don 't you, that you have a surface and you ask how
- 19 '
A ; much it will take to impart that slug?
20 !
l MR. BERMAN: That, plus two dimensional calcula-21 '
! tions.
22 DR. CATTON: Yes, but you don 't include things 23 like instabilities and the fluid coming apart while you are 24j i trying to accelerate it, so it is a very conservative esti-25]: mate.
1 ALDERSON REPORTING COMPANY,INC.
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CHAIRMAN PLESSETT: It is unrealistic. It is x_. 2I wrong.
3 DR. CAITCN: It is unrealistically conservative.
4 CHAIRMAN PLESSETT: It is wrong.
i j 5 DR. CAITON: It is a bounding calculation.
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MR. SHERRY: That is not entirely true.
7' DR. CATION: We try to accelerate liquid within 3
$ g n a pipe and with any of the kinds of pressures that you are e i I-talking about, they are not even anywhere near those kinds 6 10 i g of accelerations.
2 11 g DR. SULLIVAN: I would suggest that we let him get c 12 !
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through. They are going to discuss this in detail.
/s : .
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Then you can start with them this afternoon.
!.l 14 i y i MR. SHERRY: This is the same slide that was F 15 j ~
shown earlier for the new estimates for containment prob-16
$ ability factored into this (indicating). The slash shows H 17 j ; a relative importance.
5 18 i E l All I want to do is use this slide to show that t 19 A i if these new estimates are not correct,and steam explosions 20 !
l are really not simificant contributors to the risk due to 21l l direct failure of containment.
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CHAIRMAN PLESSETT: Thank you.
23 '
b) l 25
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ALDERSON REPORTING COMP ANY, INC,
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1 Il ,
.'C . CORRA DI'TI :
Rick has ~iven s .'rou encuc.h direction.
i 2 S3 what I will do, depending on what you want to hear, *; hat i
3; I would like to do is quickly go through a summary on the 4; t3chnical facts and then get to the technical details.
s 5! . lou know who is on the program and jou 9.new the "ei !
2 6! t probability estimate so I just want to give you an idea of N
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E of all, to improve upon the probabilities from wash 1,400 i
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n l due directly to steam e::plosion as a best estimata.
m-r 15 j And then beyond that, we should try and undarstand 16 i
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how the steam explosion fits into the overal core ne ltfcwn y 17 '
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scanario and jts t to e::pand on that f or a mome nt . .
c i r
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20 l lot of physical events that happen affect later things 21 ,i
- during the core meltdown, for instance, you gen 2 rate
- Ora 22 !
debris, solidified debrb and you are very intersstad in the ,
l l 23 charactaristic si:o of that fabris and if that f 2br is la:ar on is coolable , when it is in a debris ':in. :u also generata 25 a lar e amount of steam. And this is in a verj sh::t ameu::
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- .. - . .- - . -. ~ . - -. .. - ---
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f- s Another thing you are intarasted in in tha core !
2l meltdown accident is over pressurizaticn of the contain-3 me n t. so what you are intarasted in is a partial prassura 4l l
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O the things that can effect that is the steam explosion.
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= I g DR. CATTON: Are you going to talk about the b i -
st am explosion p saibilities in the cavity?
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. MR. CORRA DIMI : Yes. ;
16 -
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- 7 f DR. CATTON
- I think, at least for myself, I am mc e w
18 interes ted no+. in that because I have kind of writtan of f the 0 ;9 missle staam explosion as a result in the containment f ailur e.
E 6
20 MR. CCRRADI}E: Traditionally, the in-vessel ex-21 plcsion can be more damaging because you have more cen-22 s trained geometry whereas ex-vessel, it fits mora into the i,
23 overall meltdown sequence and less into a -damaging situation.
t 24l CR. CATTCN: Right, from a risk point of vi2w, it i !
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j collapse of the vapor film around the hot f uel in a contin-1 ucus medium Of coolant.
After tha collapsa, we have a very rapif haat l
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transfer and we have very rapid heat trans f ar ;ut ac 4l!
much 2::pansion. That causes a larga ;rassure ris3. ' hon e
5' Q we rapidly fragment the fuel. It is j us t a mattar of a epals
$ 6 e the heat transfer co-e f ficient times the area ti.r.as the *
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$ i Uhat changes is the heat tr ans f e r . We very rapidly 5
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cal datail because I don't knew if vou arc familiar with the 20 l orocram.
' I think some of you are not.
21 !
.irst, in terms of fuel ecolant mi::ang , rignt Scw our f ealing : that in-vessel when a significant fraction 23 af t :: 2 i molt n. This is based on calculaticas ; sing 24
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1 heat transfar in the lower planum. I N '
2, The second result is that mining is very difficult
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8 rapidly on the order of less than a couple, a tenth of a d
- s 9 millesecond or two tenths of a millesecond, and .vou cet -
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@ 10 very small fusi fragments, on the order of one. or t tc cente-z 11 meters. Sc at intermediate scale, it appears that mi::ing 3
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13 -i can mixing occur? And at 'this point, we don't think that l
w 14 t he thole core can really mix. ;1e can get into that in a 2::
9 15 g moment.
x ij 16 MR. ITHERINGTON: You said :tilleseconds, but vour g -
N I7 c hart shows seconds.
- a G 18 MR . CORRADI NI : I think I. .said one or two tenths of 19 g a second. I think I said tenths of a second. I shculd have 20 '
said tanths of a second.
21 MR. 21 ARK: Is that ?! for metric on the top?
22
- 1R. CCRRA;!DINI: Metric tons, 1,000 %ilo grams .
I 23 'l Mow, there is a mattar of uncertainty .ers and I 24 l (Q
! think this is something that I should dwell on f or a toman:.
25
, ;is have a lot of engines:ing judgment going i..to th2 pr o bat i'.1- l
- ALDERSON REPORTING COMPANY,INC.
1 458 e, 1! u.ia.s that you have seen, mainly because a 10: Of thin ~=s here l
2 cannot be proved because wa knew that the physics is going 3: to change as the scale increases.
i 4,i The first thing is we are not sure of the acda of e 5, fuel-coolant contact during the accidan: and we will get to e
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@ ! that we are not sura of the large scale effects of mining.
a r 15 0 ! On the intermediate scale, a few kilograms, a f ew t e ns of
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i kilograms , it is very easy for the fuel to min with the cool-b 17 w ant, that is, disperse itself bef ore tne enplcsion occurs. !
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= 2ut physically and I guess, intuitively, you woulf u
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20 j scala. .;nd we believe that also. Thu only thing is we don't 21 I have anperiments which essentially span the whola regime of 22 '
mass to prove it technically. 3ut that is the point at tnis 23 tim .
'That we tra planning to do in :na futura and I will 25 Just mention tais, at the end of this discal year and the
- ALDERSON REPORTING COMPANY, INC.
l 459
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j next fiscal year, we are going to continue modeling on the i
\s 2 meltdown process. But I would lika to just call jour atoention 3 among all the things we ara going to do, we are going to tr'j 4l .to go up the soals and go up to a few hundred kilograms of e
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8 i 3 6 mi::ing behavior at larger scales and see if it is indeed o
R E 7 harder to mi:: the fuel and the coolant. .
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$ 8 DR. CATTON: E AC was doing some s tudies.
J d 9 MR. CORRADIdt : Are you talking about the railroad Y
$ 10 car on the slag?
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2 11 'l OR. CATTON: Yes.
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- j 12 I don't know. I have not seen any of the results.
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13 MR . C CRRA DI FC : ' Larry Hochreiter told me about th2 ,
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14 Sut he said that the vender people did not buy it because x '
2 15 it did not sound technically sound.
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j 16 CR. CATTON: 2ecause the utility peopla don' t buy A
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2 19 i hundrad kilograms and I think you ought to taka a look at n
20 that and seo if that gives you any insight into the affect 21 of large masses.
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'2 l I MR . CORRADINI : You ma an the large 3::p3riments?
-23 ' Rign.o.
R. CATTCN:
/ 24 ' , .
I was unc,er the impression, .I was
- ! MR . C ORRA CINI
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25 ' told by the people at Westinghouse that was noo going to be i
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- perf ormed, but maybe I am wrong.
DR. CATTCN: I do not kncw, but f ;2:2 you, I would 2
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i 4 012. CC22ACIMI: I think Gary Thomas is the Contact j 0 5- person. That is fine and I just heard about it yest ; day n
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- E CHAIRMA I PLZSSZTT: *Iave you ever triad to do that.
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I n . l 0 8! MR. CCRRA DI:!I : Yes. Si. mon dard in Ingland did it. I n , \
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6 l 2 I9 - MR. C CRRA DI2II : Availability?
a 20 l MR. LI2:'H.ARD : Yes, and the avai_ ability is .much 1 1 i l 21 lass than anY ene.ra.v centent. .
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I i done positively. The only problem is to calculata tho iso-
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g r 15 s MR. CCRRADIMI: Exactly. I will get to that later.
- l 16 You are right; you are absolutal y right, that is the maximum 6 17 w
m work.
. $ 18 g To put it another way, the maximum work I could ,
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n got from a steam explosion is of the order of 30 to 40 per 20 cent of the thermal energy contant of the fuel that is involv-21 e d in it. So 30 to 40 per cent of the fuel's thermal anargy 22 s
can ultimately come out as work.
23 M2. LI2NEARD: I am surprised that calculation l } 24 j
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leaves that number that high.
25 CMAIRMAN PL SSETT: I am too, really. I would have i
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465 l If you are asking if it takes a lot of energy to
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l 4ii DR. WU: I am looking at the same thing, that is, i
-the driving mechanism and how fast would a given volume of f< . li 3 6' the fuel fragment than the surface contact area per unit Pt
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d o 9 g i MR. CORRADIMI : Y3s.
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$ I D3. MU: You procecd with that first One and I l 3.
16 ! i 4 l will come back later,
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$ l MR . CORRADI MI : It turns Out it is not vary raalis-M 18 l E tic. It is very conservative. That is the main point, be-s 19 l M cause now you remember the number I j us t quoted, 30 to 40 20 per cent. The conversion ratios are scala dependent in our 21 e::periments and may turn out to be quita low ccmpared to 22 ,
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- thermal dynamic masses, in the Order of 0 to 3 par cent, 23 in 3rfer of magnitude, f-~g 24 l (j) The most vigorous a:: plosions ara in ordar of j magnitud3 lower than the thermal dynamic ma::imum.
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6 I UOw,WO COme to a very important point and that is 2' whan wo usa actual core materials which is a coined tara, I which stands fOr L*0,, 2.R 0, , and s tainless steel, a.*.c n v o u t c l
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ALDERSON REPORTING COMPANY, INC.
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eo9 4*
I Secondiv, vou can generate dynamic prassuras which f% l 2 could fail Containment. That is, vou : uld cr ata shoch i .
3l ! pressuras that could conceivablv coucle to containment and
- i. 1 4ii failurs bv .
crackin1 l
g g 5l And the n finall.y, .vou can- cenarate action in tne e 6 e
crimarv system which can cause a small leakaga in the N
j 7l ,
penetrations. That is , you can conceive of an e::plosim n
-* 8 A in the primary svstem which does not make damaca, - d0es not d
- ! 9 z- l :enerata an.y missiles, but ::cvas the .crimar.v s.ustom.
And the O -
i- 10 ll 7
.orimarv . system, alcwly but sural.v h.v .cic.ine. is connectad' j
5 j 11l' with containment and you can increase the laakage from the I
c' 12
$ containment by the movement.
E 13 l
\ E So these are the three basic ways.
$ 14 ' r du On. CUCM:S : You must assume though that you don' t
=
.r. 15 W have the primarv. system at that time anyway. The .crimarv .
16
$ coolant piping for all purposes probably is not there.
' ti 17 ;
d x :R . CCRRADINI : Wall, .vou .; ave four 10 cps and .70u i
- n 18
- oniv . need one for a Loca so you have the other thras 1: cps t
- 19 x
s hooked up.
20 t
D2. ZUDM!S : You have One, big opening someplace, -
21 i
- 12. CCRRACII: That is right , but I am saying it 22 i
! is the r.cVemant of the sv. stem. ret pressure.
23 '
The first thing on missila generation, what .;e dif 24 j i
i was, and t' sis is going each to Dr. Catt:n's question, what 25
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f l ALDERSON REPORTING COMPANY, INC.
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l 470 l I i
' l 1; a::plosion of anorgy which ran117 is quite conservative in l
l 2i and o.# _4.a-,__'.. an4 *.".an . a va..u . . - o n s a. . v a *_ _i v a_ _$..a__-_",
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1 4 probability, the conservative probability.
t c 5 Tha ';est estimata id a was to look a: an a::plosion n '
n g 6 enerwy on the order of 3CC .a n. a " u ue ls , compare it to a n .
b 7 conservativo anorgy of about 3,000 megajuuals and then we i i
5 0l would 10ck at each of the thrac f ailure mechanisms in light d
~
n e .o. u..n. aw. .
Z. t 5 10 i l Tha first one is that we thought that 2arly time a:
=_
o vessel f ail.,r3 by a steam a:<plosion which then .:y dynamic
$ i
- 12 I
shock .Orassures would hurt containment really is n' t .00s s ible .
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$ 14 g nuclaar station.
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r 15 l Sacondiv, the weinnt ti.a .crassure,that is :he 2, .
16 '
A i 1::pansion and genaration of the missile, with the 200 mega-H 17 ,
d , juuals caso, a largo, mass missi' a does not seen 'i.:21y.
=
w
\
w 18 i -
= l And the reason thare is --ma'rba : will skin to - -
aat later, w ;
t-19 '
but the reason there is evan if you v rant very c nservative l
20 l boundary conditions and load tre upper head .iith a ' facer 21 i l s..~,
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-y .,.. s.- I 2 4.n m a *w.. .a t ,/ o u .=. a _4 _' a d - . .H. a. . , a d .'. .' .. a- '. #. . .4 "^o, 22 rathar taan a' the sidas as .ias assumed in the ".l ash 1-i C O 23 ana e, 'a is .
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- i ALDERSON REPORTING COMPANY, INC, 1
1
~ . -. .- - _ - - .-. - . .- . - . - .
I 471 i s 1 assentially opened it up like the petaling of a ficwer and 2I just eject the water Out tha top.
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.e 2 0!' abour? {
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7'I :12. COR3ADIMI: For the particular Zion fasign, :'
. n '
S N 8l think the ansver is no. I think the same calculation was j J l i i
- i 9i 2-i also done on the Indian ?oint and the same conclusi0r was ,
9 ! l r 10 i s i made. 'We are now at the procesa of looking at boiling E
~
i M 11l water ranctors to see if the conclusion is different. Me do i r it i 4
0 12 ! '
E not expect it to be. .
= '
i :i 13 ' i d 5 M0w, the c0nservative one, the conservative bound i
$ 14 l l y I is quite conservative and I think I & culd explain that. Going ,
- I t 15 ,
y back to what Dr. Linehard mentioned befora &out upper bound, ;
16 i
!a l what we did 1.s we took essentially an isotropic coolant and i
e ta 17 '
- d m e::pansion from a vapor, from a steam e::plosion and 100kad et w
. 5 18 cw the enerv.v which was verv large and considered tho 40 per fa
- 19 A cent of the core interactive with the available work in the 20 I
lower planum. That is a very larga amount of energv and 21 I I quit 3 conservative.
22 l l
What we found thera was v. ou would have many a ne r av. . -
23 ,
fissipation r.achaniOms due to :.ntarnal structuras and 24 ',
residual 30115 00:e strrture and by two-dimensional affects 25 which would nahe that quita Conservative.
1 ALDERSON REPORTING COMPANY, INC,
I i
i 472 ! (
i l
The final thing 'va did was you may not only havo i l
2, a largo maca, :ut it la quita conceivabla that i c.a t a a J :f ,
f i hrting t.u aaad by impact you or:ul.2 just inject a s ma l '. niactla I 3I 4
into tha control rod driva machaniam. And waa: la ?. .i. .I thera j waa to 133': at the impact of a small, maca misalla on tho
,n.
5' D l 3 6 control red miacile chie'd to aae if that caused aay damago
.n g which could lator cause damago to the containment.
- r. 7 And our -
I D 8,
! c onclusion was no. That docan't acom roaaonable.
n ,
'J
- r. 9, Ua too:t a range of small, masa miaila vol citics i
5 r: 10 and our conclusion was that it wculd not penetrata tao miaailo ,
n \
o 11 l ahiald and,therefora, would not even mako it to tha contain-
< 1 d 12 i
! mont. That would not cauco any damago.
z i, r
a i I will just montion uncartaintica in this araa.
13 i m
2 a 14 The first uncertaint" la 'cw roliacle arc tha con-w E
r 15 1
clusions in light of diffarant roactor designa. Uo are now 0
x s
16 in the proccas this fiscal voar of coing bac:< and loc:cing at A
j7 , boiling wator, reactor dasigns and accing if ciructurally .
a h 18 the conclusions change. Then to only did a vary simpla .
I I E"* 19 t
analyala in terms of systom gr:aa motion, re mo d e r tn 3 t hir:2
$ I 20 { f311"#3 #3Ca3013A' i
21 l i
For Cion, it showed that it was quit a r2g '.ig Lb le
! i 22 ' offect and it raally did act causa any difficulty, .ut that I i
23 is vary laalgn dopandant and 30 vo are going ;ach to the 24 reforanco al ': oiling watar in the raactor ta saa if tc.at 25 l changos. '
ALDERSON REPORTING COMP ANY. INC, 1
. . ..~ - .- - - . - - - - - . . . -
473 nc';, I would like to laave you in the summary part 1 l
, w ith , I c.uass vou could call it, the current state Of tachnolce.v.l T f j I 1
The first thing is mi::ing which is a graat un:<nown. ,
i 3l
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We feel the amount of moltan cars which can come in contact 4
! and mi:: with water, our best estimata number is 10 uo 15 e 5: .
M -
And upper bound, we think, is about 2
e e
6; .
per cent cl the core.
8 50 to 60 per cant.
7 es -
. U Why such a larae upper bound? -
3ccause we don't E 8, N i
'd understand t.M physics of mi::ing to be quite honest. We
- 9 z.
feel that 10 or 15 per cent may be too high, but 50 or 50 10 \
z i E cer cent is the upper bound because we do not thin:t that z
< 11 ) i 3 l
- 12 ' <
more than'about 50 cer cant of the core would avon be
~z l' E molten at the . time of fuel-cociant c:ntact. The rest of a 13 l
- i 5
x 34 ' the 40 per cant is probably sitting on the .cerie-harv. in a ,
W -
- .~ So that is an upper 15 solid stata as partially disruptive.
W
=
.- bound is Our Sest estimate.
3 16 l s !
p 17 In terms of the conversion ratio, we thin': ba tre
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$ 18 ' e::perime:t s with corium A =av indicata that they very low -
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H c:nversion ratics, less than .1 par cant, ar2 c.ulta .or:babla
=
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20 ! in the cor2 T.e ltdown. And we wouM hound this by tha v2ry ,
i i
21 vigorous e:: plosions and tha acscciated conversion ratics 22 .ath the ::ltan iron and a'.uminum :::ide simulants.
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23; 22. 202A;3: This . 1 was based on cir 2::ps:- , t l
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./ w 4, a lower vessel wall and fall right into the reactor cavity.
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U a::plosion is -coing to have to hap.oen in the first fe'/ seconds
- n. 7 .
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, of fuel-coolant contact or elsa che material is ~oin: - . to be 8 t
- e solid or. partially solid.
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3 whereas in terms of melt through on the vessel,
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.- 16 , you only convert .001 to machanical energy, does that mean that B !
us i s.i 17 ; you are laft with the debris pile in the bottom of tha plenum w
x
% 18 and it is a lot hotter so that it would have a fastar melt ;
tx 19 through? Or is it e:ccass energy that is not converted to n
20 mechanical energy, just steam that sort of bubbles away?
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i ALDERSON REPORTING COMPANY. INC.
i i 476 l
- 1 1
I would a:: pact, the fuel-coolant incaracti:n is :nly :ne bound l
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- D 8 mi.:< . It f alls to the bottom, the solid bottom. It recon-0 9
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z boilin~: with notthe overivin~. . boiling watar and 31:wly but
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d 12 :
E l DR. C.TTTON: This wou'd laad to the most rapid i
m 5 13 4 E penetratica :f the vessel.
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i that ha.e.canad is that it stratiliad.
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" CH I.T !;i3 PLESSCTT: Uhat la it that you are pro-J
- 9 z- posing to do '.iith your prasantation acw?
h 10 i
M2. C ORRI DI NI : I wantad to go thr: ugh tha techni-E_
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cal datails af how we came to tha conclusior.s f:: '. a r c. a 0 12 >
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I4 i CH.'.I22!A U ?L2SS CTT : It is not a mattar Of interast.
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It is a mattar of time .
16 -
3R. CATTCU: Just one thing that I would lika to
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E ! haar about. In their racant taat, fragmentatica is an
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19 a
M description Of what they have found about fragmentation, I
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I, F its 2. If you would tall ne about Fits 3 and Fits 4, maybe l l
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n 5' This is a oictura of what it looks like when it b N
9 g 6 mixed. Je have five kilograms of moltan macerial coming in n-n' 7 These are the explosions.
,- to about 250 kilograms of water.
n
- 8' M These are not the proportir.nal masses. It is the lucite water d '
t 9{ chamher of about 2 and one-half feet bv. 2 fan b.'r 2 feet in x-t 10 t y, depta squara area.
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A .' 12 . CCRRIDI;II:
- It is dumped in suddenly.
l 20 Dennis Mitchell who was in charge of the 2nparimeno 21 ;
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water and then it mines due to ; oiling and hydro d; namic 23 crocesses.
So that is what it looks 1133 when you nave a 24 l 1
'me.e dec. er. and allow it to min.
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as it occurs with time. First it comes. in and,as I was telling
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2l _you, it ccmas in as a mass of matarial. It antar: the i I
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4 bottom aid the tri~v.c erin:. evant ore.cac.ates or it e::01:das m., 5 hamispherically.
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m 6 CHAI2 MAN PLZSSZTT: Is that e::plodine- watar?
17 il 7 MR. COR2 DIGI: No, . this is spontaneous. Tha -
r,
,3, 8! reason it is spontaneously triggering the bottom. I would I
J l 9j like you not to .ask .me because we - don' t have good physical z
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CHAIRMAN PLESSCI'!: I will not ask then.
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M2. CORnIDINI: 'So that is what happans.
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5 14 i M:w, the debris, I am going to have to shew Fits 1 w
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. 16 I can give you the datails of the other ones.
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- N l7 DR. CATTON: I want the mass weight and maan DJ m
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E 2 .:L'. . CIRRIDINI : You will get '. t . HatJ in thara.
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I have to be quick before it burns up my pictura.
21 This is Fits 1-A whera thers was no c::pl;siOn.
22 It ssentially went i.to the water and it mi::ed with the watar.
l 23 It fell at'the bottom and it quenched as debric. Iha :sss 24 mean diametar. hare was three millameters, five kilogra. s Od l\ 25 ! l i ;
matarial. Uhat this is a pictura of is all of the debris that 3
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ALDERSON REPORTING COMPANY. INC.
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1- is greater than 500 microns. .;nd I want to get across to you I.
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I -433 Fits 4 was the same initial conditiom as Fits 3, 1
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! five Nilograms, e::capt we raisad the ambiant pressurs 10 bars, 2
'll' bars, I am sorry. And wo got no s::plosion Sacause the 3, 5 I 3pontaneOus trigger was suppr3ss3d by the hi Jh 3:3s3u:2.
4, Fits 5 *.las the. sam 3 as Fits 4 e:tcept that Ne in- , e
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- ributad an artificial triccar -- which gave us bach the a::pl:sion g 6j ,
at high prassure.
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7 . 3 DR. UU: How was it administered? 8 A" i
'd LG . CORRA DI NI : By a detinator.
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;- 1 The' measured impluse was 700 Newton seconds.
r: 10 ! . z ! 5 DR. CATTOU: What would happer. if I doubled the mass e 11 ll , 3
,, to 10 kilograma? What is your best guess?
- 12 z~
I 2-13 ! i SD. C ORRA DINI: On which Of those'five tosta? e 3
- 14 i
CR. CATTON: On Fits 3-A. a w
- V 5 15 :IR. CORRIDINI: I to uld gat another e::pl:sim with w
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16 the same conversion ratio. 3 A g* j7 j DR. CATTON: Uhat was the conversion ratio? i a m
$ 18 3G. CORRIDIdiI: In Fits 3-A, we estimatad it to be
{ h 19 i hetween 2 and 3 cer cent. It was a very vigorous 2::plosion. 1K I M i 20 l The only other thing I wanted to talk about was 1 21 hollia?. l 1 22 CHAIRMAU PL2SSETT: Scw long is that going to taha? J l 23 ' ' 2e honast, { 24j . D. . CORRIDI;iI: 2a hanast.' Four minutas. I only l 25 t have two viawcraphs, i ! l t
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l ALDERSON REPORTING COMPANY. INC. l' .. . . . _ _ _ _ _ _ -_ __ _ , _ . _ . _ _ . . . _ _ _ , _ _ . . . _ _
434 CEIRMN PLZSSETT: Four minutes is all y0u hava. l LL', . C CRRI OI' I : Uhac we have d0ne is la :ava done 2j i t
. pa r i.na nt to lock at .;oiiing ':chavior wi h:ut :aa 2xpl:si:n.
3i t a the . larch model whien is a naltdown coda, they assume that 4 onca tha moltan matarial :cmas in to the wacar in the , o i ranctor cavity it dispersas in a diamens: which is var-4 f n ! small which the user can . cut into the ccmo. uter ceda, . R. / 7 Physically this is not tha case. Tm only way 0 " 8 t e j this could happen is if the debris would fluidi c, tnat is, d 9t l ?- it would cc=c in and 21:: to a diamatar which was small g 10 E anough that you would essentially levitate the particias bv = ' p 11 the film boiling that it creatas. c 12 ' Tha lower bound.cn that is the order of t.io or thron " i millimotars, varv small.
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$ 14 ( w $ The other sida of the coin, the other sida Of the P - 15 w 16 spectrum is if you drop in the matarial it gcos in and it s' 9 l falls firectly to the bott:m. It racongicmeratas at ::h e 17 i b w ' = M 18 bottom and assantiallv vou hava film boiling from a strati mad E , layer of molt to the cooling.
, 19 2
;iew, why is that s o important? Re.ne mb a r , I said 20 the staam a:: plosions are cnly important in terms :2 failing 22 Containment. Another thinc, : hey are important in malt down 23 , accidant to datarmine the rata of staara prassurinati:n in r
24 containman; bacause that could f all contairmant .;y : var 25 prassuri; tion, much .nora probabla evant. So partial i i i
! ALDERSON REPORTING COMPANY, INC.
d 485 1 pressure is very important. i JG 2 This e>:perimant was done to see on the grascura ' 3 history, tamparature history, in a scaled, close chamber 4 with 21 kilograms of iron aluminum oxide fuel dumped into e 5 44 kilograms of saturated watar. I don't have the data 9
$ 6 because we had to do a pre-prodiction. We had to be fair N
$ 7 with ourselves and' I did .the prediction and Denis fid the -
n j 8 e:cpe riment. I d
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9 att to give you an idaa of the model, what we ; z- < 10 z essentiallv. did was that we did a ver.v sim. ole medal. se- 1 11 A cause I did a pro-pradiction, you can't know what happens 5 g 12 about the mi::ing before it happens. You have to bound it, a 5 13 ( = So I :cok ono bound being 'the fluif and limit of two c. illa - h 14 meters and another bCund being the stratified li. nit as it
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15 " 6 f alls in and mi::es, recong10=cratas and stratifies. If
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16 s v5 it fluidi:3s in the a: periment without an e::plosion, you N I7 w would have predictad based Or. condensation 20dals and boil-
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ti 18 ! _ ing models about si~wht and one-half bars of peak pressure. j 19 If it stratified, I fon't see the and point, but 20 l it is about 3.5 bars peak pressura and this is the came graph 21 of the stratified case showing the temperatures on the sida, i 22 l 3:w, why de I shcw the stratified case again? 23l' . I Becauss it turned out that when jcu look at the films, i: r 24 i ' stratifiad. t Uhat is the peak prassure en the 2::parima nt? 25 , The peak prassure on the a::p3riment was 3.3 bars. 20 we ALDERSON REPORTING COMPANY, INC, I l
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I l l l l i l l 43G i li , fid a .cratt." vcod .iob in .tradictin . the and pressure based 1 2l l On (arived condensatica ncdals and boiling :0dals, assumng l I 3: wo know he., tha thines mi::2d. - 4! i Ca. CATTON: Is this a new numbering system. It I I e 5 says Fits ;-G. 9 l ,3 6: .'4P, . C Pm . .. sI .' ~2
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n ' & 7 c:<periments I just have baan talking about. ' ] 8l I just wanted to get across that idea md I am done, d - 2 9 CHAIRMAN PLZSSCTT: Thani .vou verv. mucc.. z. @ 10 ' ue will go into one more item on our agenda which z = { is lI j is back to you, Harold, I I2 DR. S ULLIVAM: I assume you want to hoop this briod. 13 The first one Ne were talking about the sa.niacale j 14 t. led 5 svstam which I assucae ycu knew is the a a W desien h: ~ 15 6 , for the samiccalo facility. We nota :n the first slida that = i j 16 it has a lot of support. The problem is the Jundtng for it, s U- I7 i' w = And that is what we are workinc on ncw. - $ 18 He have a lot of technical supp0rt. C g 19 l Locking at the status of the Mcd 5, tc.e dasign work l l 20 ! was terminated in June of 1930 and it was strictly due to the
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1 21 i funding limitations. He icra 2::pe ctinc. to get a larr.ar i 1 22 i suppiament from the T:.'I and ue had taken a '. t of money out 23 of the semiscale to do scoe T'-c icrh and we just did 70t get all of that money back. S: .;e had to terminata che f.asign 25 l for the Dd 5
.I I ALDERSON REPORTING COMPANY. INC.
i 437 1 The_ secondary design and the hardwara associated with
, 2 that was tarminated in september Of 1930 and thera is a in the.
3 latast fraft of our five .*raar . clan, we ara inCicatine that - 4 ve would liha to .oroceed with r.etting fundin- w fr:m all t.vres e l Of sources :utsida the agency and that is '.lhat we ara N currently pursuing right n:w. 3
- 6 n
R 7 Tha preliminary design work was completed. He have E n s 8 the cost schedules which are comolated and thera is no con- - g struction work curruntly in progross. 9 i 5 10 If _'rou remater that Idaho gave us the f=sien f or " Z 5- two facilities, one was commonly r eferred to around ucr.': 11 4 a z 12 as the "al chcapo," and the :ther one was a" basi: Cadillac." 3
= 13 Lat me go through those tto Options a little hi .
b l*. 14 ! i First of all, tha chaapar version wa cahin:' - the 9 4 E a r 15 Moda 2-A v2ssal that we have ri-ht now and hee.':ine- - en Onca s 16 through a staam generator and parforming a limitaf amount
- si g 37 of tests and then raconverting the system back to the Med 2-A w i b 18 and continuing the tasting.
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t-3 n 39 The nuriers that I remarbar were arounC 53 milli:n.
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to ans'.;er cuastions that tera Scund to come up in '.c.a cheaper 24 versi0n.
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-l t 439 f or th2 ope ration. He don't see that we could aff:rd to 1lI 2l operata both . f acilities at cr= '- 4
3 ,;a think that the casting would probably la-in the i , 4l ! ordar of t</o' years from FY '04 to '35 g 5.i In vour handout, there cra a number of othar 'riaw-
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4 ! 0; 2 ; graphs and ' they go through the - tests that we thuugh ra wou3 N b 7 ~ lika to Se conducting in tin Mod 5 facility, then what we A j 8 thought we could do between n:w and the FY '91 to tha time that J-9
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z . i the Mod 5 f acility and the ned 2-A or the vestinghousa o 10 D z geometry. So you can breece through those at your ocnvenience.
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< DR . C UDA MS : Is this M0d 5 intended to be located 3 1 ' d I 2 12 l' in the sama, precise spot whera Med 2-A is?
3 13 l
\ j O?. . SULLIVAM: Ho, as it turns Out, t0 Continua tha
$ 14 I g
.:e Mod 2-A tasting there is a north and south cell and I forget 9 15 C which one the f acility is in now, hut when we would use to z
16 l clean out the other call, it turns Out that it is actually
* !# 17 d
x to an advantage .to use that other call because che heights 6 W 18 are a problem in the building. You need to raise the roof cr t 19 ' 2 go down dcaper. There is Sedrock under the facility so that 20 cell is actually deepar and there would have to Sa soma 1 21 l constructi:n work done to f.ig out the Other cells, 30 we 22 l would - 13ava the 2-A f acility whera it is and put tha Mod 5 in 23 l; the other facility that would all w constructic to ;r: grass 24 l parallel t: tasting in the 3catinghouse 2-A desi:n. 25 , EIInn ?L2SSETT: I do not think thera tro any ALDERSON REPORTING COMPANY, INC.
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-i90 l questions.
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! That !:eing the casa, 1 2 31;. . . .,c
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22 23 24 25 ALDERSON REPORTING COMPANY, INC,
I i I 1 e 1. l This is :: certify :ha: the attached pr0ceedings before tha i NUCLEA R REGUL\ TORY C0:@ FISSION l 1 in the matter Of: Date of ?recteding: Ja nua ry 14, 15, 1981 Docket lumber: none Place of ?receeding: A lb uc ae rc ue . New Mexico were held as herein appears, and tha: this i s the Original :ranscri;; thereof for the file of the 00c=ission. 1 James W. Higgins . Official Reper:er (Typec) 4 +4> j b = %M
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Official Re;0rter s'Sigr.ature)
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