ML20153B351
| ML20153B351 | |
| Person / Time | |
|---|---|
| Issue date: | 11/02/1978 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1588, NUDOCS 7812040048 | |
| Download: ML20153B351 (36) | |
Text
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- ,! J m ISSED: p NOV P' d ,j d h MINUTES OF THE REACIOR FUEL SUBCOMMITTEE MEETItK; OCIOBER 4,1978 W\SHINGION, D.C.
AcR.5- / 583 PDR '%i/71 On October 4, 1978, the ACRS Reactor Fuel Subcommittee held a meeting in Washington, D.C. , to continue review of the NRC Reactor Safety Re-search program in the area of reactor fuel. The notice of the meeting appeared in the Federal Register , on September 15, 1978. !b requests to subnit oral or written statements were received from members of the public, and none were made at the meeting. Attachment A is the mneting agenda. The attendees list is Attachement B. A tentative meeting schedule is Attachrent C to the minutes. Attach: rent D contains selected slides and handouts used at the maeting. A complete set of slides and handouts is attached to the office copy of these minutes.
OPEN SESSION (4:05 p.m. - 6:50 p.m.) INTRODUCTIOj Dr. Shevnon, Subcommittee Chairman, called the meeting to order at 4:05 p.m.
The Chairnnn explained the purpose of the meeting and the rules and proce-dures for conducting the meeting, pointing out that Dr. Thomas G. McCreless was the Designated Federal LT.ployee in attendarce. Dr. Shewmon called upon Dr. William Johnstor., Chief, Fuel Behavior Research Branch, to begin the day's presentations.
Dr. Johnston reviewed the discussion items for the meeting and introduced Mr. Richard Sherry to give the first presentation.
WATER RFACIOR SAFETY RESFARCH FUEL MELT PRO 3 RIM - R. SHERRY, NRC-RES Mr. Sherry discussed the objective of the Fuel Melt Research Program and noted that the program is divided into two major areas: (1) phenomena affecting contaircr.ent integrity; and (2) fission product
. Reactor Fuel Meeting 10/4/78 transport and release. Mr. Sherry also noted that NRC is participating in, and conducting information exchanges with, foreign safety research programs in these research areas. A Sandia representative is currently stationed at KFK in Germany to report on research underway on core melt /
concrete interactions.
The fission product release and transport studies were described. The objectives of the program include characterization of the rate and quantity of fission products released, and development of correlations and models to characterize the radiological source term resulting from a fission product release. Tne research programs underway in this area were also described (Fig D-1) . Funding for FY 78 and FY 79 will be $650,000.
Work is underway at Oak Ridge, and Battelle Columbus Laboratories. Melt-down source-term experiments are being conducted in Germany, and NRC intends to contribute funding to this program. The BCL work includes developmant of the TPAP code designed to model ficcion product transport and attenuation outside the primary system, within the containment.
Results of the fission product release and transport studies to date indicate that releases of iodine and cesium from the fuel will be factors of 60 and 200, respectively, less than gap release assumptions in current studies. In response to a question from Dr. Shewnon, Dr. Johnston noted that the fission product release fraction discussed is independent of fuel burnup.
Mr. Sherry reviewed the core melt / concrete interaction studies presently underway at Sandia Laboratories. The NRC Advanced Reactor Safety Research Group is contributing funds to these studies, primarily for application to the IMFBR. The program will examine: (1) large and small scale experiments interacting nolten core materials with concrete, (2) simulant tests of melt behavior in contact with concrete, (3) response of concrete to intense heat fluxes, (4) studies of the thermal decomposition of concrete,
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. .' Reactor Fuel Meeting 10/4/78 and (5) determination of gas and aerosol release characteristics. 'Ihe FY 78-79 operating budget and test program were reviewed (Fig D-2) .
FY 78 funding is pegged at $385,000, decreasing $320,000 for FY 79.
Sipificant results obtained to date indicate that the concrete erodes j primarily by melting and that spallation is unimportant to concrete integrity. It was also noted that the gases liberated fran the concrete 1
are chemically reduced by the melt, and significant a~ounts of non-radioactive aerosols are generated. An advanced concrete / melt inter-action code (CORCON) is under development. In response to a question from Mr. Mathis, Mr. Sherry said that the concrete erosion rate is not a strong function of the type of concrete involved, however, the amount of gas released is. In response to a question from Dr. Shewmon, Dr.
Johnston noted that the principal impetus for this study arises from the Reactor Safety Study core melt scenarios, as well as an ACRS request that the Class 9 sequences noted in WASH-1400 be better understood.
1 Dr. Ohrent asked a series of questions centering on the decision as to whether or not an adequate amount of information has been obtained from the core melt / concrete interaction program. He asked if this program would be flexible enough to obtain informtion on alternate means of containing a core melt, such as using water piped through the contain-ment base mat to facilitate heat transfer to and from the molten material.
Dr. Johnston noted that when the program was established two years ago, it was agreed that it would end in FY 79 and obtain information cri melts at the 200 kilogram size. Because of budget problems, a larger experi-mental program is not possible at this time. However, NRC intends to contribute support to the large-scale German experimnts in this area.
Dr. Mark asked if the large amount of hydrogen generated as a result of the melt could be acconnodated by the hydrogen combination systems pre-sently used in plants. The NRC Staff replied in the negative.
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. caacte r reting 10/4/78 The Resea:cn Program in the area of steam explosions was discussed.
The prog n objectives are to identify and understard steam explosion triggering uechanisms, and estim te the probability of containment failure by steam explosions.
s Steam explosion research is underway at Argonne and Sandia (Fig D-3) .
Sandia is also participating in a steam explosion research prcxgram being conducted in Germany. Details of the Steam Explosion Research Program are showed in Figure D-4. FY 78 funding is $610,000, ard decreases to $540,000 for FY 79. Research results to date indicate that elevated steam pressures are effective in reducing the probability of vapor explosion, and that vapor explosions can be produced without an artifical trigger at atrospheric pressure. It was also noted that the size of the explosion does not appear to affect explosion efficiency.
Mr. Sherry noted that the indication that vapor explosion probability is reduced in the presence of elevated system pressure would be applic-able to meltdown accident seguences involving high containment pressure.
Dr. Shew ton, referring to an earlier discussion indicating that the fission product release may be much less than preserstly assumd, asked if this inft,mtion could be used in licensing analyses. Mr. Meyer noted that the Accident Analysis Branch could irdeed use this informa-tion to, for instance, revise assumptions in the Regulatory Guides.
GOALS N;D PRIORITIES OF NRC FUEL bel %VIOR RESEARCH BRANCH - W. V. JOH'JSTON Dr. Johnston outlined the short-term and long-term goals and priorities of
- the Fuel Behavior Research Branch. He noted that the Subcommittee was pro-vided two documents, the first is a budget breakdown of the Fuel Behavior Research Branch programs (Figs D-5-7); the second document is a description of the PBF test program (see attached reference sheet at the back of these minutes).
act w ting 10/4/78 D.O insto:- uscussed the separate effects test program in the clad cod fml areas (c nj IF5) . He noted that most of these programs are due to be comple M by FY 79. 'Ihe exception to this are two programs in the ciadding area: the Multirod Burst Test Program at Oak Ridge, and the PCI f : ess/Ruptur e " Zircaloy Program at ANL. Both of these programs are r.cheduled to tc ~ oinate in FY 82. Two other programs continuing beyond FY 79 are an ANL study of fission gas release, and a Battelle PNL program invo.1ving the experirrental verification of steady-state fuel codes.
Dr. Johnston reviewed the in-pile test programs conducted at PBF. NRU, f
and e,erseas reactors such as Halden, PHEBUS (France), and ESSOR (Italy) as shown in Figure D--6.
I There was an extensive discussion of the in-pile test programs, centering on the Justification for the PBF reactivity insertion accident (RIA) test .
program and to a lesser degree on the NRU IEA tests. Dr. Johnston noted that the NRU program will attempt to obtain experimental information on l
heat transfer across the pellet-to-rod gap, as well as obtain information
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l on scaling of reflood phenomena (NRU tests will be conducted at full scale). Dr. Meyer (NRR) noted that the RIA experittents are intended to examine the question of the effect of pellet cladding rrechanical interaction causing failure of the cladding at low energy deposition for high-burnup l l
fuel rods. Tests conducted at the SPERT reactor showed fuel rods with burnups of about 30,000 tWr/ffrU that failed at very low energy insertion rates ( 90 cal /gr) . Dr. Okrent was of the opinion that based on the day's l presentation, the NRU tests do not appear to be particularly applicable to fuel-related research activities. He also felt that the PBF RIA tests may not trerit their current high priority, since the principal accident of concern here (rod ejection for PWR, rod drop for BWR) is believed to be a low probability event. Dr. Johnston noted that the original PBF program plar.
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- Reactor Fuel Meeting - !-
10/4/78 arranged the test priorities, at the behest of the ACRS, in the following order: ICM, LOCA,;and RIA. He also noted that three years ago IGC-NRR requested by formal letter that the RIA tests be given higher priority. {
Dr. Okrent also expressed concern whether or not the PDF test program is addressing. the' potential of fuel melt leading to flow blockage and possible propagation of the melt. Dr. Johnston replied that the PCM test series has indicated that fuel failure propagation is highly un-likely. As a result of further questions on this topic, Dr. Shewnon suggested that the Subcommittee could draw up a list of questions to be sent to the NRC Jtaf f for response to Dr. Ohrent's concerns. In response to a question from Dr. Shewnon regarding the PBF PCM test series, Dr. I Johnston provided the information shown in Figure I)-8.
l Dr. Johnston discussad PBF test plans beyond 1981. He noted that preliminary plans call for five-test-a-year schedule, with three RIA-type and two A'IWS-type tests. %e RIA tests will include study of the effects of high burnup on rod integrity. 'Ibe possibility also exists for additional LCCA-type tests, pending evaluation of presently scheduled IDCA tests.
Dr. Johnston discussed future program efforts in the area of fuel code j development, and nolten fuel and fission project release and transport.
He noted that future code work will focus the code optimization to reduce
! running time and nake the codes more user-oriented. We fuel codes will also te coupled with thermal hydraulic codes, such as REIAP and COBRA.
In the area of nolten fuel and fission product releast and transport, NRC will complete the work on fission product release from nolten fuel in 1979, and follow the German study in this area af ter that. The Battelle Columbus TPAP code will be complete in 1982. Work in the study of vapor explosions will continue at Sandia until 1982 as well. In the area of concrete / melt interactions, NRC will complete intermediate-size experinents l 1
this year, and then follow the German large-scale experiments that are l scheduled to begin in 1980 and run for four years.
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i
Reactor Fuel Meetin9 10/4/78 l
Dr. Shew:on recessed th? m <
.cS' p.m., to go into open executive session. ,
OPEN EXEC 11 RIVE SESSION j6:50 _ - 7:21 p.m.)
The Subcommittee discussed the information heard at the day's meeting and exchanged opinions regarding information that should be discussed in the Subcommittee's report on reactor fuel research. Among the principal l
items noted in the discussion were the following points: (1) Dr. Okrent felt that the ECCS Subcommittee should 63 contacted to determine if they have examined the proposed LOCA fuel test to be conducted at the NRU Reactor at Chalk River, Canada. He had reservations regarding the justification of these tests from a fuel behavior standpaint; (2) re- i garding the PBF-RIA test series, Dr. Shewmon said he would attempt to l address the topic of the relative priority of the RIA tests in the draf t report on the NRC Research program. Dr. Okrent said that he did not understand why NRC has such a high priority on the RIA tests; (3) Dr.
Shewmon said he would like to see a resolution of the ACRS generic item dealing with fuel failure propagation. He felt the Subcommittee should determine whether NRC is, or should be, addressing this generic item, and whether the PBF tests, for example, will resolve this problem.
The meeting was adjourned at 7:30 p.m.
IUTE: A transcript containing additional details of this meeting is available in the NRC public Document Room, at 1717 H Street, N.W., Washington, D.C. A copy of the transcript can also be obtained from Ace-Federal Reporters, Inc., 444 North Capital Street, N.W. , Washington, D.C.
4
In accordance with the procedures
- Dotm1F HuCtf AR SCrfMCT ADYt10tY con. portions of the meeting when a tran-
- knitt (NU$AC),19r8 fMitVMENTATK)N script is being kept, and questions anny outlined in ihe ProruL Hrcisin en
- be naked only by memt ers of the sub. Octot>cr 31.1977 (42 F7150972), orn! or
?.USCO MITTU committee. Its consultants, and staff, written statements may be presented o M"*9 Pert,ons desiring to Inake oral strLle. by members of the public, recordmgs ments should notify the designated will be pennitted only during those
. In accordancevith the Federal Advi- Federal employee as far in advance as portions of the meeting when a tran.
sory Cornmittee Act, as amended. Pub. practicable to that appropriate ar. t.cript is being kept, and questions tr.ny I 92-453, the National Gelence Foun. rugementa can be made to allow the be raked only by members of the Su:>
dation t.nnounces the following tacet, necest.ary time during the meeting for committee, itA consultanta, and ets.ff.
gng: Persons desiring to make oral stMe.
such statc tnents.
A ,;NAMTl: DOE /NUSAC. Instrumenta- The reenda for subject rneeting ments should notify the designat4d tion Subcommittee. shall be as follows: Federn1 employee os iar in advance ta DATC AND TIME October 7,1978,0 practicable so that appropriate t.r.
WEmSDAY, Ocrosnt 4,1078 rangementa can be made to allow the a.m. to 6 p.tn.; October 8,1978, D r m. necerzary time during the meeting fer to 12 noon. 4 r.u. UNT11, Tur coNcLU: Ion or PIACC Conference Room 338, Na- sosuus such Thestatenients"for agenda subject meeting l tjonal Scienea Poandation. Washing
- The rubcomm!ttre may meet in ex- shall be as followr' ton, D.C., telephone 202-032-4310. ecutive se-slon, with any of it.c consul-WfMESD^r. Onosta 4,1978 l TYPE OF MELTINO: October 7,1573, tants who inny be present, to explore r.nd exchange their preliminary opin- urETrNG Vnl.1. Comu%ce AT 8:10 AX !
open: Cktober 8,197S, open. I lons regarding rnatters which thould COWi%CT PERSONS: Dr.Howel O. be considered during the meeting cnd The subcommittee tray meet in ei. i Pugh.11 rad, Muricar Science Scctica, to dhcuss the subcomin!tice's preparr.- (CLitive r,cssion, with any of its cc r.r.d-Room M1, Nntfunal Science Pounds- tion of a repart to the full committcc tr.nts who mty be present, to exp'cn: i tjon, Washington, D.C., telephone 20h on reactor fuel research. and exchange their preliminar7 epr.- l 632-4318. At the conclusion of the executive fons regarding matters which shr a!d I
SUMMARY
1/.ImrIT.S: Mry ba ob. tesslen, the e.ubcommittee wul hen.r be considered du-ing the meethe n.d to dheuss the Lut,cormnfitee's prep.t.
tained from the Cc,m nittcc Mr.nr.p- presentation by and hold discuesfons nent Coordinulea htMf, Dhtston of with reprcent4.tive.) of the NRC staff ration of r. report (.o ilw f ull Co nmP,-
Financia.1 nad Ad:rJM tn.tive 14rnt ge- r.nd thctr corwultantz pertin:ent to the LeeAt ou Imprc 'cd rsf cty :Tr.ter.t.
the conclu>toa of the execu M ment, Roo:n 2 G, Ib tlonti Science above topics. The subconimittee may Poundation. W: ineten. D C. 200LO. then caucus to determhc phother the teufen, the Subcomittc wiS har
^ .
matters identified in the inittal secalon prctentations by r.nd hoM discustcr 3 PURPO"" Or ' "drI I t . o ot d T n fe h her dd t I tr on th f f [e 1 3
!c nuclent ociace in ttc United j j' nt;gn pe g thtn caucus to detcimtne whetMr the inatters identifh d in the initL.1 r,m .
topics to be disept. sed, whether the br.re been rdeaunely covered r. .d AGENDA: Turmulat!on of Sukommit- rnecting has been canecled or resche- whether ndditional meetings on this tee n:tivities for the next G montbs duled, the Chainnan' ru1!ng on re- tode are necer y.
Dated: September 12.1978' quests for the opportunity to present ParWer Wodon remw oral rtatemen% and the time rilotted topics to be dir. cue.1, whether t M. Rrr.m.dnrm, therefor can be obittned by a prepaid meeting has baen canceled or rwc,he u e.
Comr.utkc Mecrem ant telephone enU to the desirnated Fed. duled, the Chairrran's ruling en re-Coordin:I.or. eral emploWe for this meeting, Dr.
[FR Doc. 78 2e,005 PDod t-l b70; tM5 rm1 Thomas G. McCrclus. telephone 202- c;uests for the opportunity to preen 031-3267, betscen b:15 r m. and 5 p.m., eral stattments, nnd the time allo'a3
_ therefor con be ootained by a pn;L gg, telephone cad to the designated Fed.
[757 M 1] eral employee for this meetint, Dr.
Dr6ted: ScPtC5bC# 12* 107".' Thomas O. McCtelen, telephor,e LW-NUCLEAR REGULATOW (/ John C. Hoy!c, 634-3207, between 8:15 rum. nnd L p.m COMMIS5fDN Advisory Committee e.d.L.
ADVT",3RY CcmurTri on EEACTot stFtr. Management O//scer. ,* * * '
GuuL!, St.'r,ConsTTEE oH REACTO2 [FF Doc.n 20072 Imd S-14-78; D:45 r.m1 Jorrn C. Hoy1.r, Ntt Adenory Committee NNPcN"! O!/lce'n 2
[7590-01] [FR Doc. 78-25073 TUed 0-14-78; 8.45 m)
The ACRS Subcommittee on Reno-tor Puel will hold an open meeting on ADVISORY COMMfTTEE CH MACTOR SATE.
October 4, ID73, in Room 1046.1717 H GUARDS, 50BCO/UAnTtt ON UNPROVED Street NW., Washington D.C. 23555. $ATETY a s w as [7393_gy}
to continue its review of NHC research d^8 ADVISORY COMMITitt ON REACTO: 1AM-on reactor fuel for consideration by GUARDS, 50*COMwtTit CN *tuAL13T the ACRS in its prepa.rntion of a The ACRS Subcommittee on Im. AND l'tOf>AMt1$TK A1$l11MtHT report to Concreas. proved Safety Systems will hold an In necordance with the procedures open meeting on October 4,1978, in I cutlined in the Ibrut. Rt.ctsTr.n on Room 1167,171711 St.rcet NW., Wash.
October 31,1977 (42 FR 56972), oral or incton, D.C. 20555. to discuu the NRC The ACRS Subcomroittee on ReU-
. Written statements may be presented plan for rc. search to irnprove the abihty and Probablit.stic Assesst.wnt by members of the public, recordings safety of light-watcr nuclear power- will hold an open meetLng on OctcLer will be permitted only during those plants. 4,1978, in room 1107, 1717 H Streft MDLRAL Riot 1T[t, V01 43, NO. ItMEIDAY, StrTIMMt li,1978 A T Tt W / M n f A
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,. REACTOR FUEL SUBCOMMITTEE MEETING .1 OCTOBER 4,1978 WASHINGTON, D.C. /'
ATTENDEES LIST ACRS NRC P. Shewman, Chairman R. Meyer, DSS D. Okrent, Member K. Kniel , DSS J. Mark, Member W. Johnston, RSR W. Mathis, Member R. Sherry, RSR T. McCreless, Staff
- A. Marchese, NRR P. Boehnert, Staff
- Designated Federal Employee s, 3, .J-
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ATTACHMENT B
-.,..........,_9,._,.
i ACRS REACTOR FUEL MEETING ,
OCTOBER 4, 1978 i.
WASHINGT0tl, DC .
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l TENTATIVE SCHEDULE OF PRESENTATIONS 1 4:00 pm I. IffTRODUCTION.
P. SHEWM0!! - CHAIRMAft >
ll 4:15 pm .
II. FUEL BEHAVIOR RESEARCH BRAl'Cil PROGRAMS .
W. V. JOHNST0!1 ..
A. CORE tiELT AND C0!! CRETE INTERACTI0i!S B. FISSIO!! PRODUCT RELEASE AllD TPJt!! SPORT 5:00 pm III. GOAL.S AND PikIORITIES OF FUEL BEHAVIOR RESEARCH DRANCH W. V. JOHNST0t1 A. SHORT TEPJi (2-3 YRS) GOALS AND PRIORITIES B. 10NG TERM (4-5 YRS) G0ALS AND PRIORITIES
~ 6:00 pm IV. ADJ0URil .
Please confine presentation times to about one-half the time allotted to allow for Subcommittee ~ questions.
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FISSION PRODUCT TRANSPORT RESEARCH i
> ' - - FY 78 - FY 79 PROJECTIONS ....
FY 78: OPERATlflG FUNDS - 650K ,
COMPLETE LOCA-TYPE (500-1200C) SOURCE TERM EXPERIMENTS (ORiiL)
COMPLETE MELTDOWii SOURCE TERM EXPERIMENTS (GFK)
DEFINE EXPERIMEflTAL NEEDS FOR VERIFICATION OF LOCA MODEL (BCL)
, MODIFY TRAP FOR MELTDOWil ACCIDEiiTS (BCL)
FY 79: OPERATION FUNDS - G5E COMPLETE HIGHER TEMPERATURE (1200-1600C) SOURCE TERM EXPERIMEf1TS AS SAFETY CONSIDERATI0ilS ALLOW (ORNL)
CHARACTERIZE MELTDOWN SOURCE TERM (ORNL, GFK)
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DEFINE EXPERIMENTAL NEEDS FOR VERIFICATION OF TRAP-MELT CODE (BCL)
CONDUCT LADORATORY SCALE SEPARATE EFFECTS TESTS FOR TRAP- ,
MELT CODE DEVELOPMENT EXTEND TRAP CODE TO MODEL FISSION PRODUCT TRANSPORT AND DEPOSITION PHENOMENA IN THE MAIN CONTAINMENT
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MOLTEN FUEL - CONCRETE INTERACTIONS STUDY l
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FY 78 - FY 79 PROJECTIONS FY 78: OPERATING 385K COMPLETE SHORT--TIME (5 MlfD, INTERMEDIATE SCALE (~10KG)
IllTEGRAL TESTS.
DEVELOP ADVANCED INSTRUMENTAT10ti COMPLETE SUSTAINED HEATil1G (15 NIfD, SMALL SCALE (~'2KG)
INTEGRAL TESTS ,
DETERMINE FISSION PRODUCT RELEASE BY SPARGING SEllSITIVITY STUDIES WITH liiTER CODE AVAll3GILITY OF LARGE SCALE (200KG) UO MELT FACILITY 2
(UiFBR PROGRAM)
FY 79: OPERATIONS 320K COMPLETE SCALING ANALYSIS --
COMPLETE SEVERAL LARGE SCALE EXPERIMENTS DEVEl.0P AND VALIDATE ADVAtiCED MELT-CONCRETE INTERACTIONS
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[ CODE '0RC0fb 1 TERMINAT IVITY ASSUMING ALL SAFETY-RELATED PHEll0MENA HAVE BEEN ADEQUATELY CHARACTERIZED Y
ELEMENTS OF STEAM EXPLOSION PROGRAMS ANL - SIMULANT FLUIDS IN FREE CONTACT HOMOGENEOUS. NUCLEATION l
SYSTEM PRESSURE AND TEMPERATURE CRITERIA ,
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- l CHEMICALCONTRIBUTl0NS
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- LARGE SCALE NACL / WATER EXPERIMENTS (ISPRA) i i 9ANDIA - ANALYSIS OF MELT-WATER CONTACT PROTOTYPICAL MATERIALS IN FORCED CONTACT (I.E.,
. ARTIFICAL TRIGGER) i PARAMETER VARIATIONS IN SYSTEM PROPERITES SCALE EFFECTS i
EXPLOSION EFFICIENCY l
h ANALYSIS OF CONTAINMENT FAILURE
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STEAM EXPLOSION RESEARCH FY 78 - FY 79 PROJECTIONS FY 78: OPERATING 610K DETERMll1E EFFECTS OF MASS OF liiTERACTANTS (SIMULANT FLUIDS)
ON EllERGY C0f1 VERS 10N EFFICIENCY AND DETERMINE EFFECTS OF CHEMICAL REACT 10fiS (AfiL)
COMPLETE SMALL SCALE (25G) TRIGGERING EXPERIMENTS (SANDIA)
COMPLETE RELATIVELY UNSOPHISTICATED INTERMEDIATE SCALE (5-20KG)
EXPERIMEllTS WITH PROTOTYPICAL MATERIALS (SANDIA)
FY 79: OPERATING 540K C0!1STRUCT IllSTRUMEllTED TEST CHAMBER AND PERFORM INITIAL lilSTRUMEt1TED lilTERMEDIATE-SCALE EXPERIMENTS (SAi4DIA)
C0llTil!UE SCALING ANALYSIS (SANDIA, ISPRA)
DEM0ilSTRATE HIGH PRESSURE AND HIGH TEMPERATURE CUT 0FFS USING b'ATER AS THE WORKING FLUID (SAtlDIA, ANL, ISPRA)
DEVELOP MODELS FOR PREDICTING PROPAGATIDIl AND FRAGMENTATION PHEN 0MEllA ASSOCIATED WITH STEAM EXPLOSIONS PROVIDE QUANTITATIVE PREDICTI0 tis 0F PROBABILITY AllD CONSEQUENCES OF STEAM EXPLOSIONS (SANDIA) l COMPLETE ENGlflEERING ANALYSIS OF PENETRABILITY OF CONTAINMENT BY MISSILES GEt1ERATED DURING STEAM EXPLOSION (SANDIA) 4 D4
8/23/78 -
FUEL BEllAVIOR RESEARCH BUDGET BREAKDOWN Financial Identification Number Titic Laboratory FY1978 FY1979 FY1980
- 1. Fuel / Clad Model Development Experiments A 2016 Fission Gas Release ANL 368 320 One-third 4
8 2043 Expt. Verification of PNL 675 690 Half Steady State Codes B 2040 Decay Heat Analysis Oregon State 20 - -
B 0095 Decay Heat 8,.r Spectrum ORUL 175 - -
B 5984 U02 Dimensional Stability Purdue 42 - -
B 6274 Gap Conductance U. Mo. 26 25 -
A 2017 Mech. Properties of ANL 582 - -
Oxidized Zircaloy .
A 2017 Characterization of ANL '
- 150 -
Anisotropy of Zircaloy A 2017 PCI n. css / Rupture of ANL - - Increase 7,
, 21rcaloyt)'l"d ,~u!
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B 0120 Multi-Rod Burst Tests ORNL 1200 1200 Three-fourths enj,sm % 7 A 4068 Mech. Properties of BCL 550 570 -
' IrradiatedZircaloj B 0124 Zircaloy Clad ORNL 465 415 -
Creepdown B 5948 Clad Stress / Strain U. Fla. 250 270 -
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B 7012 Decay Heat LASL 42 -
PHL 47 $2 -
B'2278 Res. En9. Cadarache Subtotai Model Devel. Expts. 4442 3732 Half 1
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- t Fuel Behavior Research Budget Breakdown /
Financial :
ldentification Laboratory FY1973 FY1979 FY1980 t tivmb,t;r Title
- 2. Fuel Irradiation (Other Than PBF) t;RU PNL 2300 1905 Double B 2277 Foreign Assignnents Undes 6 53 Continue B 56S5 Halden Project 258 400 Continue B 5531
- Esso.t' hv.D yn(& % B<3 n W (&tru g guy) 2564 2358 Double Subtotal Fuel Irradiation
- 3. Pouer Burs, facility Experimental Program Experimental Engineering INEL 6888 7065 Increase A 6041 PliL 900 1400 Continue B 2084 Test Train Assemblies Subtotal PET Exot. Program 7788 pfq3, increase
- 4. Power Burst Facility Operations
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PBF Engineering IliEL 1450 1990 Two-thirds A 6044 ,
" PBF Operations IllEL 2654 2560 Continue A 6057 ,
IfiEL 1925 - Continue A 6095 Improved PBF Performance Experimental Program INEL 340 715 A 6124 Requirements Subtotal PDF Operations 6369 5265 Reduce D-4
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O Fuel Behavior Research Budget Breakdown _ Financial Identification ITGEber Title Laboratory FY1978 FY1979 FY1980
- 5. Fuel Code Development and Assessment A 6050 fuel Behavior Model' IfiEL 500 550 Continue Development A 6046 fuel Behavior Analysis IfiEL
- 1748 .175 Continue Assessment
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Consultants 6 Subtotal Fuel Code Development 2254 1725 Continue
- 6. Molten Fuel and Fission Prnduct Release 6 Transpo Q A 2029 Vapor Explosion Triggering AfiL 160 40 -
A 1030 SteamExplosionPhenomena[<9 Sandia 450 500 Continue A 1019 Molten Core / Concrete Sandia 385 320 One-fifth Interactions
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A 1206 Resident Engineer-Karlsruhe Sandia 91 95 Continue B 0127 Fission Product Release ORiiL 340 200 -
B 0189 Fission Product Transport ORiiL 115 - -
Fissica Product Transport
- Undesignated -
500 -
Test Facility ; m., ,/4 /
A 4078 BCL 296 250 Continue TRAP Code Development gg. g,g ,
A 40" Pool licat-Transfer Correlation OSU 45 - -
- Separate Effects Tests Undesignated -
200 Continue TRAP-DEtiT Consultant 4 - -
" Subtotal Fission Product Transport 1886 2105 Hal'f nTOTAL FUEL BEHAVIOR RESEARCH 25303 -23650 Continue g--,
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TEST CATEGORY - POWER-COOLING MESMATCH (PCM): .
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NUMBER OF TESTS - 11 4
SPECIFIC TEST TEST OBJECT!VES PARAMETERS --
CHF SCOPING e DETERMINE FEASIBILITY OF o COOLANT FLOW & INLET ENTHALPY
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4 PCM 8-1RF 4X TEST!NG o ..
PCM 1 TEST P,OD POWER o MEASURE CLAD OXIDATION o INITIAL PLENUM PRESSURE
! PCM 2A o MEASURE CLAD CALLOONING o .
P.CM 2 OR COLLAPSE FLOW & POWER GNANGE RATES. .
PCM 3 o IDENTIFY FA! LURE (TO ACHIEVE SELECTED COMBINA- .
PCM 4 PROPAGATION TIONS OF AP & CLAD T VS TIME) -
PCM5 o < IDENTIFY FLOW BLOCKAG_
PCM 6 c (DENTIFY SCALING EFFECTS
. PCM 7 o ESTABL!SH CHF/DNS REPEATABILITY --
j AND EQUIVALENCE OF POWER .
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4 INCREASE VS FLC71 DECREASE .
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