ML20030A517

Burnout Limit Curves for Bwrs, Class 1

ML20030A517
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/01/1962
From:	Imhoff D, Janssen E, Levy S GENERAL ELECTRIC CO.
To:
References
APED-3892, NUDOCS 8101090836
Download: ML20030A517 (53)

Text

,.

- -,. n

_c

..~

4

f ~/pa.w/Be i,,,.

:.. ;;;i:::

12w w

s.-

6,)

am,

. JR APast 4 W42

~mr.trq M. @ -(ss 3s.

sc

• • m.c,1 4 4

~

3

. +

=

e-*

f BURNOUT llMIT AilRVES FOR

~ BOILING WATER-tEACTORS

(

RY E. J AM55EN

.e

5. LEVY N

/j s

tl Jh g

g k g ':

4 h

' d' f

G g

.~~

• h is e

t, q n l,,* - v J-

. n :-

- c..

.:: c - _.

titult PIlit itIlPN[Il IEPAIINEIT

'n '

GENERAL $ ELECTRIC

._ ~

811 laII, tillfilull

'.....=2 u

i:.

~

e-g/o/of,.orsMC??00R10RIGINAL

-- ~~ a.

_ -. a

APED-3892 CLASS I 619-TIO 2 BURNOUI LIMIT CURVES FOR BOILING WATER REACTORS h7 E. Janssen and S. Levy April 1, 1962 t

Prepared 4 :

MMJW ansfen E.

S. Ied Approved W: 9 lf d d D. H. Imhoff, M6nsger Engineering Development ATOMIC POWit (GuiPMENT DEPARTMENT GENER AL h ELECTRIC

$ AN 101E, C AliFCINin gr v-

DISCLAIMER OF RESPONSIBILITY This report uas prepared as an account of research asd des elop.

ment u ork performed by General Electric Company. It is being m.sde asailable by General Electric Compans uithout considera.

sion in the interest of promoting the spread of technical knoul.

edge. Neither General Electric Company nor the indis idualauthor:

A. Atakes ar.; uarranty or representation, expressed or implied, uith respect to the accuracy, completeness, or usefulness of the information contained in this report, or that the use of any information disclosed in this report may not infringe prisately ou ned rights; or B. Assumes any responsibility for liability or damage u hich may result from the use of any information disclosed in this report.

LN.2 I

TABLE OF C0h"fDITS Page No.

Bumary 1

Introduction 2

Ihsis for Reconstended Curves 3

Limit Curves Based Upon APED Internally 4

Heated Annular Tests

!Odified Limit Curvec 8

Recommended Limit Curves for Resctor Application 14 Application of Recommended " Burnout" Limit Curves to 14 lbdified Annular and F111tirod Geometries Application of Recommended " Burnout" Limit Curves to 15 Other Geometrica Notation 17 References 16 LIST OF TABLES Page No.

Table I APED Regular Annulus Burnout Data 19 Table II British, Italian, and U.S.1hternally Heated 20 Annulus Burnout Data,1000 psia Table III APED Special Channel Burnout Data, 1000 psia 21 Table IV Italian and U.S. Circular Tube Burnout Data,1000 paia 22 APED Rectangu.lar Data,1000 psia SUZ'ARY

" Burnout" limit curves are reco: mended for the design of boiling water reactors.

%e recommended curves cover the following range of conditions:

Prcosure 600 to 1450 pain 0

2 Flow rato 0.4 to 6.0 x 10 lb/hr-ft Steam quality subcooled to 45 per cent by weight Hydraulic diameter :

0.245 to 1.25 inch Heated length 29 to 108 inchea

%e basis for the " burnout" limit curves is discuaced and their application to available data is presented.

i - -

INTRODUCTION In boiling water reactors, water enters subcoded at the bottom of the reactor and emerges at the top as a steam-vater mixture. As it flows along the fuel assembly, the water removes heat generated within the fttel rods and boils at the water-fuel interface.

If more,and more heat is generated in the fuel rods, the number of steam bubbles at the water-fuel interface increases until, at the critical heat flux, the fuel surface becomes blanketed with steam.

Maen this happens, the fuel surface temperature rises rapidly, often leading to

" burnout" or failure of the fuel clad.

De existence of a " critical" or " burnout" heat flux value is without doubt the most in:portant themal perfomance limit in boiling water reactors.

It restricts their power output and requires that they be designed to operate at a prescribed margin under the critical heat flux. This margin, as shown in Figure 1, is established by considering the axial distribution of heat flux and steam quality in the " hottest" channel or fttel assembly of the reactor. We heat flux plotted in Figure 1 is taken at its highest expected value and includes allowances for gross radial neutron flux distribution, inter-control rod peaking, maneuvering, transients, and instrument and operational errors.

Similarly, the flow through the fuel assembly is appropriately reduced to account for flow naldistribution at the core inlet or possible flow redia'tribution between fuel bundles during overpower conditions.

Chee the heat generation and flow rate are established within the hottest fuel assenbly, it is possible to calculate the corresponding coolant enthalpy in the axial direction. As shown in Figure 1, the coolant enters the core in the subcooled state and does not reach saturation conditions until it has procccded some distance from the inlet.

Beyond this point, steam quality increases gradually and reaches a maxit:um at the core outlet. At every '

positirn nimg tha fuel cir: ment it ir ponoibl3 to specify o uzitical heat flux value correnponding to the calculated steam quality, coolant flow rate, and 61ven bundle geometry. Bis is 2tpneented in Figure 1 by curve AA.

We shall concern r.ure'slves here with the establishment of curve AA.

Curve AA is usually obtained from out of pile tests simulating the geometry, flow rate, pressure, and coolant enthalpy of the hottest channel. De purpose of this rt port is to review the available experimental results in the range of interest to boiling water reactors and to derive from these data a set of "bumc.ut" lignit curves which can be used in the design of boiling water nactors.

BASIS FOR RECO!OSTDED CURVES M>st boiling water reactors utilize multirod fuel assemblieo.

In this type of geometry shown in Figuro 2, fuel rcis are arranged in a aquaru array con-tained within an unheated fuel channel. Bere are variations in size, spacing, length, and number of fuel rods from one reactor design to another. Bere are also variations in the type of spacers used to keep the rods in transverse

=14gn= nt.

Two typical spacer geometries are illustrated in Figure 3 In the Dresden type spacer, the fuel rods are kept apart by a solid plate perforated for water passages. In the other type spacer shown in Figure 3, two rows of wizwe att intertwined between rods to obtain proper alitasent.

LI addition to the mechanical and geometric variations, the canditicas which detemine the critical heat flux, namely flow rate, coolant enth21py, and pressure, also change with each reactor design.

De multitude of reactor design conditions is auch that prototypical tests to cover them all are not poscible. Yet, a set of buzuout limit curves must be developed that accounts for all the important variables.

'lhis was accom-plished here throuGh a step-by-step appzt>ach.

It consists of: -

1.

Infining limit curvas bassa upon extcnsive critterd heat flux data obtained at General Electric Company in an intom'dly heated annulus.

S e internally heated annulus geometry vus selected because it simulaten one of the three possible fuel cell geometries shown in Figure 2.

It is not only representative of comer rod conditions, but it also has the highest ratio of unheated to heated surface area. As such, it gives the lowest critical heat flux value of the three possible fuel cells since the " burnout" point has been found to decrease with increased uaheated surface area.( }

2.

Modifying the above limit curves to necount for lover trends or special effects reported in some instances by other experimenters. his insures that differences in test loops and experimental techniques or conditions are included in the reco= ended curves.

3 Considering data obtained in multirod geometries or annular geometries modified to account for flow redistribution, presence of spacers and rough surface conditions. Bis step verifies that the limit curves developed for a normal annular geometry can be applied to reactor type multirod systems.

4.

Comparing the recommended curves to other available data.

Bis final check gives an overall perepective of how the proposed limit curves fair with respect to other test results.

LD4IT CURVES BASED UPON APED E7fERNALLY EATED AmlVLAR TESTS Re most extensive series of tests with an intemally heated annulus has been perfomed at the Atomic Power Equipment Department (APED) of General Electric Company. Se APED data constitute the most complete set of critical heat flux values obtained for this type of geo=etry.

It includes variations in heated roi

-h-I

diacster and length, annulus thickn:ss, flow rata, brat flux, coolant cnthalpy, and pressure. Se specific conditions under which the data were obtained are Most of the test results have been accumulated recently(

listed in Table I.

and are censidered on the whole to be quito accurate because of their con-sistency, reproducibility, and independence from the characteristics of the loop external to the test section.

Detailed discussion of thoce annular data is given in reference (2).

Six independent variables in addition to the critical heat flux are considered there for correlation purposes. Scy are: heated length, heated rod diameter, hydraulic diameter, flow rate, coolant enthalpy at the critical point, and pressure. Bree of these variables, namely, heated length, rod diameter, and hydraulic diacator, were found to have a negligible effect upon the correlations within the following range of conditions:

0 375" to 0 540" Rod diameter:

D

=

Hydraulic diameter:

D

0.245" to 0 500" g

29" to 108" Heated length:

L

=

600 to 1450 psia Pressure:

P

=

ne results are illustrated in Figures 4, 5, and 6.

Figure 4 shows that a change in heated length from 9 to 6 feet does not influence the critical heat flux value. Data for two different flow rates and two heated rod diameter sizes are plotted in Figure 4.

The illustrated trend is in agreement with results reported by other experimenters.

It is now generally accepted that the heated l

length has only a small effect upon the critical heat flux except for very short i

lengths which lead to increased critical heat flux. Note that the heated lengths used in reference (2) are about twice as long as those found in actual nactor cores, and the limit curves based upon APED data are expected to be conservative

• Uhe cloacat approach to the critical heat flux (see Fig.1) happens in most reactors a short distance beyond the mid-point of the reactor so that heated lengths to the burnout point rence from 10 to 60 inches.

vith respect to this variable.

Mgure 5 considers the role of heated rod dianctor. Test results obtained at APED vith 0 375 and 0 540 inch reds are plotted tocether with recent columbia thiversity(3) test data for a large heated rod of 1375 inches. As shown in Figure 5, the critical heat flux value is independent of the heated rod size.

Figure 6 illustrates the effects of changing the hydraulic diameter from 0 335 to 0 500 inch. Within this range, typical of most reactor desicas, the role of hydraulic diameter can be neglected. A small effect of hydraulic diameter has, hovaver, been noticed in reference (2). We critical heat flux value was found to decrease with increased hydraulic diameter and appropriate corrections for this trend beyond the rance of 0.245 and 0 500 inch are developed in the next section.

Iet us next consider the remaining three independent variables of pressure, flow rate, and coolant enthalpy and try to develop a set of limit curves based upon them. The annulus data of reference (2) at 1000 pain are plotted in Figures 7 to 11 for flow ratert G/10 less than O.4, 0.4 to 0.6, 2

0.6to1.2,1.2to1.8,and1.8to6.0lb/hr-ft. A lower bound, or limit, has been drawn for each case, belov which no data points appear (except for one point in the subcooled region of Figure 11). The range of qualities covered by the " burnout" data can be divided into three agions: Icv (including subcooled ccnditicus), medium, and high. The limit is seen to consist of three connected straight-line segments, each sec=cnt being the limit for its respective rcC on.

Examination of Figarcs 7 to 11 reveals that i

1.

no limit for the hich quality zucion shows no flov effcet, being the same for all the flova. Limitations of the APED annular test facility actually precluded operation at hich flow rates below the limit in this recion. Se limit here is therefore m CNshig }imit and we need to refer to data outsido riCD to establish a limit curve at hidt flov ratos in the high quality region.

2.

Be limit for the m:iium gr.lity recion chova a definite flow effect, the hicher nov civing the lover position for the limit at any given quality. For examplo, at x e.16 the position of the limit decreacca with incroacing flow as follova:

lobrent nux, nov Fate, g

c/ lob 2 2

(lb/hr-ft )

(

. r-ft )

.4 to

.6 77

.6 to 1.2 555 1.2 to 1.8

.42 1.8 to 6.0

.29 he limit in this region is clearly a voll defined burnout limit below which no burnout has been e::perieneca in the range of con-ditiens previcusly lioted.

3 We data pointo in the low qa:lity-subecoled region are fever and less donco, especially at lov flow ratos, so that the limit for them is not as charply defined. Heverthcleco, the li.::it for this region shows a definito flow effect which is innuenced by the state of the fluid, i.c., by the degree of quality or subcooling. At lov qualities the invorno relationchip between flow and pocition of limit exists as it did in tho Irt.dium quality region. But as the subcooling is increaced the relatienship cha Ces no that at a subcoolin6 of bh,/hfg = 0.12 the positten of the limit inerences with increasing flow.

Ih other voras, in moving from the quality to the subcooled rocion the limit for the hich flow data crosecs over the limit for the low flow data. S o limit in this recien is a lino belov which no bumout has been experienced. However, because of the limited amount of data (48 points total) we need to look to other data to assist in establishing a burnout desica limit at low qualities.._

'D es off; cts cf cysten pressure rim abovn in Figures 12 to 15 2 3 cxperi-montal data of reference (2) at 600, 800, 1200, 1400, and 1450 psia are plotted in Pit aco 12 to 15 for flow rates 0 0 of 0.4 to 0.6, 0.6 to 1.2, 1.2 to 1.8, and1.8to6.0lb/hr-ft. %e limit curves obtained for 1000 psia continue to serve an lover bounds for data at different pressures if the critical heat flux (pDO)P "I' a pressure P is adjusted to 1000 psi according to (NBO)P.1000 /440(1000-P)

(pBO)P vbero P is the syatem pressure in psia.

Wo effectiveness of this simplified pressure cornction tem is illustrated in Ficures 12 to 15 Its validity is confimed by 130 experimental points plotted above the limit lines. Only six test points fall under the limit curves, and all six of them are very close to the bounding curves.

It should also be noted that according to Figures lE to 15, the critical heat flux decreases monotonically with preneure over the testod range of 600 to 1450 psia. Bis trend has been confirced by other experimenters.(1)8 b)

FiCurea 7 to 15 define the desired set of limit curves for an intemally heated annulus. Bey are based exclusively upon APED data.

IAt us next con-sider how they might be modified to satisfy results of other experimentera.

MODIFIED I,DLIT CURVES,

It was pointed out in the previous section that we need to refer to additional data to modify APED annular limit curveu in the high quality regicn at high flow rates, the lov quality zone at low flow rates, and over the entire quality range for hydraulic dianeter well outside the range of 0.245 to 0 500 inch. Appropriate modifications to the APED annulus limit curves in these three areas are offered below.

High Quality Region Critical heat flux data in the high quality region at high flow mtes have

• Inter modifications to the limit curves shown in Figures 12 to 15 move 5 of these six points above the recommended bumout limit curves for rec.ctors. ~

recently been reported in reference; (1) and (5) for.n intenutlly hented 5

annulus. Se results from refersncos (1) and (5) are summarized in Tablo II ar.d are plotted in Figure 16 tocether with a few points obtained by columbia

}

thiversity.

Superposed are the limits for the APED annulus data at three 4

4 flow conditions. N British and Italian results of mferences (1) and (5) are relatively consistent with each other. Howevar, with respect to the previously j

discussed annulus lianit curves, they tend to be low in the low quality region, are high in the middle > j on, and are low again in the high quality region.

At low qualities and low flows the curves through the British and Italian data are similar to curves obtained in reference (4) when conditior.o in the I

i loop were hydraulically unstable, It in believed that an unstable condition i

j may have existed at low quality in the ' British ur.d Italian tests which would s

result in lower points.

(his will be discussed further in the low quality l

section thatfollows.)

j Ih the middle quality region the bumont values obtained by the British and Italians fall above the APEL limit curves and they do not require further l

consiieration he m.

h the high quality region the low values obtained by the British and Italians are believed to be due to the n.ethod. they emplo/ed for bumout detection.

Reir system dettets a very small change in the character of nucleate boiling rather than a substantial one which is acconqpanied by surface teatperature i

increases of 50 to 100 F as doce at APED. Nevertheless, the Brit'sh and i

i Italian data provide the only basis for establishing a burnout 2.imit in the high quality region at high flow rates. Se recoussended curves of Figures 7 to 15 in this region have, hafore, been modified to be consistent with the British and Italian results. Se proposed changes a m shown in this m gion by dotted lines in Figure 16.

I e

2e Columbia data am rather limited and scattered and they were not given too much weight here.

• • Subsequent reports from CISE note the occurance of instability in this region.

.g.

Iow Quality Region a

l Several experimenters have mported the existence of a maximum and minimum i

critical heat flux in the low quality region at low flows. Bis type of performance is illustrated in Figure 17 It is suspected that critical heat flux curves of I

the kini shown in Figure 17 are obtained when the test loop is hydraulically 4

unstable. Se APED test usults do not exhibit this trend. However, until this i

j phenomenon is completely understood, a horizontal limit line drawn as shown in l

Figure 17, should be used to account for its ocasible occurrence.

he appropriate location of the horizontal limit lines was obtained from data aported in reference (7) at 2000 psia for a variety of non-annular geometries.

R ese are the only extensive results available in the low quality-subcooled region I

I in addition to the APED regular annular dats.

3h order to specify the horizontal limit surves, a method similar to the method proposed in aference (8) for sub-i cooled pool boiling was used to predict "bumout" in subcooled fomed convection flow. Se critical heat flux is obtained by adding thme heat flux tems, one of which takes into account forced convection:

[Totalheat

[ Pool boiling Additional Additional a

! heat flux ati

/

flux due to

/

flux due to (fluxat (burnout (bumout

/

subcooling forced convectiorg his was done for the 2000 psia data of mference (7) and the ratio of predicted j

j critical heat flux %, to monuma critical heat flux pM dehmined. Se cal m l

lated ratio is plotted versus flow on Figum 18.

l

%e ratio, %p/% s in spite of showing considerable scatter, is definitely a M

function of flow. Se ratio is seen to exceed unity especially at low flows.

It is felt that the data points above unity in this low flow region fall in the same category as the British and Italien annulus data at low qualities, i.e.,

the test loop was hydraulically unstable. A limit line to account for such instability can be drawn as shown in Figure 18 to bound the calculated ratios on the ;.typer side (except for three points which are too erratic to give any credence 4 -

to). Se ratio given by this bounding line was then used as a correction factor in predicting a corresponding burnout limit at 1000 psia.

Se limit so detemined (banca initially cn 2000 psia data) is a competing altemate to the APED annulus limit in the low quality-subcooled region. To give some welcht to both liuits but still to be cease"intive the following procedure was adopted:

1.

If the new limit van above the APED annulus limit, then the APED annulus linit was used as the " burnout" limit in the low quality region.

2.

If the new limit was below the APED limit, then a horizontal line was drawn throuch the intersection of the new limit and the zero quality axis," and extended until it struck the APED limit. This horizontal line would then be the "bumout" limit in the low quality region.

Recomended " burnout" limit curves at 1000 psia have been papared, based on the considentions of the data as discussed in the two foregoing subheadings.

6 R ese curves are shown in Figure 19 fu C.ov rates 0/10 of 0.4, 0.6, 1.2, 1.8, 2

and6.0lb/hr-ft.

Extrapolation of these :urves to other pressures between 600 and 1500 psia is obtained by addition of the previously discussed pressure correction tem.

IIydraulic Diameter Data which show the effect of burnout of increasing the hydraulic diameter well beyond 0 500 inch are quite sketchy. Some data have been taken at APED in an intemally heated annulus (2) at a hydraulic diameter of 0.875 inch (3/8 inch 0.D. rod in 1-1/4 inch tube) and in the obcervational test section at a hydraulic diameter of 0.60 inch (1/2 x 2 inch channel). (9} But very few of these points were taken under conditions identical to those for the smaller hydraulic diameters.

• Figure 18 dcale with subcooled conditions. The use of zero quality or zero subcooling insures that the lowest horizontal curve that can be obtained from Figure 18 is drawn.

11

b4 h Hence, direct co=parison between hydraulic diameters 0.875 and 0 500 say, is almost impossible. Ucyorthelecs, we have proceeded with the limited amount of available data to devise a correlation which includes the hydraulic diameter as one of the parameters.

Ec difference betvcen the burnout heat fluxec pg and p corresponding to a given difference in hydraulic diameters D and D is obtained from g

H2

-d d (DHa - Dal ) (x - a)

B02 m

where 6

0.0714 (G/10 ) - 0.220 a

6 2.19 x 10 d

D

hydraulic diameter, inches H

2 G

p mass velocity, lb/hr-ft BO Wis expression was checked against the ' intern 911v heated annulus data 0.245" and 0.495" and against the observational test section data taken with D :

H (rectangular ::hannel, both sides heated) taken with Dg = 0.445 inch and 0.80 inch.(9}

R e check was made as follows: A best-fit curve was drawn through the data points for the cealler hydraulic diameter. Another curve was then constructed which lay below the first curve by the calculated difference %B01 ~ B02' corresponding to the difference in the two hydrarJic diameters. Bis second curve was then compared with the data points for the larger hydraulic diameter.

Goodacrocmantvouldshowthattheexpressionfor%B01 ~ B02 can be used to predict the effect on burnout of increasing the hydraulic diameter.

Figure 20isaplotoftheannulusdataatG/106 = 2 lb/hr-ft2 for Dg = 0.245 inch and D3 = 0.495 inch. ne curve throuch the DH = 0.245 inch data points is a best-fit curve. We dashed curve is the prediction for D e 0.495 inch, as H

explained in the preceding paragraph. We D e 0.495 inch points agree with the g

12

predicted curve to vithin 8 per cent. Cb tha same figura a o plotted tha test reaultsatG/106=056lb/hr-ft2 at Dg = 0 335 inch and Dg: 0.875 inch. Be predicted curve at Dg = 0.875 inch cnce again agrees with the experimental points within 8 per cent.

Figure 21 is a plot of the rectangular channel data for a 0.010 inch heater 2

atG/106: 0 72 lb/hr-ft, for D

0.M5 inch and DH = 0.80 inch. Be dashed g

curves are the predictions for DH: 0.80 inch. The points agree with the pre-diction to within 10 per cent.

The agreement between predicted and measured values in Figures 20 and 21 is considered good enou6h that the expression for % g1 - dB02 has been used to 3

predict a set of burnout limit curves for D : 0 75 1r. h, 1.00 inch, and 1.25 inch.

H Se basis 10 the set of curves given in Figure 19 for hydraulic diameters 0 5 inch and less. %e curveo at higher hydraulic diameters are plotted in 2

0.6,1.2 and 1.8 lb/hr-ft Figuren 22, 23, and 21+ for flow rates G/lO mis co::pletes the modification to the original APED annulus limit curves.

As we review the changes included up to this point, ve note that they always introduced further conservatism in the limits. Fbre specifically, one can state that 1.

No data exists from any source of which u have knowledge which lies below the recom= ended curves in the medium and high quality regions, except for a very few isolated and highly questionable points.

In contrast, there is a great quantity of data which lies substantially above the reccc::= ended curves, from British, Italian, Russian, and L

U. S. sources.

2.

W e date which exists which lies below the reco= mended curves in the low quality region consists essentially of only the three points in Figure 18 which weis neglected in drawing the limit line, p

3

%e data available at hydraulic diameters well beyond 0 5 inch are as q

W I

.g Y',-

al

~

4 y2t com2vhat limited, me recommended curvas are probably quita con-servative, especially for hydraulic diameters greater than 0 75 inch.

_R_ECO:C'E:iE3D LIMIT CURVES FOR RFACTOR APPLICATION Figures 19 and 22 to 24 are the recommended " burnout" limit curves for boiling water reactors at 1000 pain.

In order to facilitate their application to reactor design, Bray (lO) has recently propoce1 a set of algebraic equations to descrite them. She recommended equations at 1000 spia are:

d /106: 0 705 / O.237 (G/10 )

x 4 xt 6

B0 6

x x 4x4x l

yB0/106 = 1.634 - 0.270 (0/10 ) - 4 710 1

2 6

6 p30/lo = 0.605 - 0.164 (c/10 ) - o.653 x

x 4*

2 6

0.197 - 0.108 (c/lo )

vbere x :

1 6

x2 c 0.254 - 0.026 (c/lo )

Sis correlation is valid over the range of interest to boiling water reactors.

6 2

It covers flow rates up to 6.0 x 10 lb/hr-ft and hydraulic diameters below 0.6 inch.

At pressures above or below 1000 psia, the burnout heat flux is obtained by adding the following pressure dependent tem to the heat fluxes given by the t-above correlation (N o)p, looo / 440 (1000 - P)

(N )p 8 30 3

j For hydraulic diameters beyond 0.6 inch the above critical heat flux equations are modified as follows for x > xy?

W

36) (x - a)

(

N jf!)f (M o)p 3

g DO

[5" m

i.

APPLICATION OF REC 012ETDED "BURNOITf" LIMIT CURVES TO MODIFIED ANNULAR AND MULTIROD GEOMETRIES yn e

"';j Several modified annular and a limited number of multirod geometries have been

• Ibr x /. x, subcooled data was used and in the subcooled region the burnout y

heat flux is independent of hydraulic diameter. __

tested at APED. Rese special che.nnel geo=:trics are quite diffarent from that of the regular annulus. Ley include tests with multimd assemblics of 3 and 9 rods, eccentric annuli, annuli with cm211 and larce clearance, sandblasted heated rods, heated rods with simulated spacers, and annuli at very high steam quality. We condition for these various tests are sus:arized in Table III. Their results serve prit:arily to point up the fact that vide variations in test ocction geometry do not greatly change the " burnout" characteristics.

SLe APED special channel data are plotted for flows G/10 less than O.6, 0.6 on, respectively,. F1 ures 25, 26, and 27 The to 1.2, and 1.2 to 1.8 lb/hr-ft 6

recommended reactor limit curves are superposed for comparison. Except for a few isolated and questionable pofats, the p yosed limit curves for boiling water reactors also serve as a limit for the special channel data.

Bey, therefore, apply to eccentric rods, much rods, rods with simulated spacers, and multirod geometries.

APPLICATION OF REC 0KEIDED "BUMIOUT" LIKET CURVES TO OTHER GE0METRIES R is category includes data obtained at other establishments in circular It also includes data obtained at APED in a rectangular channel.(9)

Me tubes.

specific test conditions concidered are sumarized in Table IV and the experi-6 mentaldataareplottedonFiEures28and29forflowsG/10 less than 1.2 to 1.8 2

lb/hr-ft. The recon:nended reactor " burnout" limits are superposed on the same ficures.

The experimental results are videly scattered, but again the recomended 1

limit curves serve as a limit for the data in this category, except for one sin 6 e e

isolated point.

This serves further to point up the fact that the propotied j

g

,v limits apply to a multitude of geometries.

It is noted in Figures 28 and 29 that the APED rectangular channel data fall F#

vell above the results obtained with an internally heated annulus. This is under-li e

standable since, as previously noted, the critical heat flux decreases with the u

iM wp M

^

amount cf unheated curface area. In en canular Cec stry, water nnst stectmulata en the unheated surface of tho ennulus thus reducing the burnout limit for this geocietr/. -

a i

t -

v P

f i

i J

,f

NOTATIOIT i

B Icas dimension of rectan%r croso section, inch C

Short dir:nsica of rectansular cross section, inch D

Bod diatster, inch 7

D Hydraulic din =cter, inch H

G thss velocity (1b/hr ft )

h M cnt heat of vapo d aM cn (Btu /10 fg A h, m.m.c mgn)

L Heated lenSth, inch P

System pressure (psia)

X Steam quality, non-dimensional Heat flux at buniout (Btu /hr ft )

B0 2

p Bitrnout limit heat flux (Etu/hr ft )

g 2

Q Maasured burnout heat flux (Btu /hr ft )

M p

Predicted burnout heat flux (Btu /hr ft )

p 1

l l

_PQFf.~ I2lCES 1.

Silventri, M., Two-Phase (Steam and Water) Flov and Heat Transfer, International Heat Trnnsfer Conference, Paper No. 39, Boulder, Colorado, August 28-Sept, ember 1, 1961.

2.

Jannsen, E. and Kervinen, J.

A., Burnout Limits for Single Rod in Annular Geometr/, 600 to lh00 psia, GEAP 3899, April 1962.

3 Blackford, D. and 1.htzner, B., Basic Experimental Studies on Boiling Fluid Flow nnd Heat Transfer at Elevated Pressures, thiv. of Columbia, August 13, 1961.

4.

Aladyev, Miropolsky, Doroshchuk, and Styrikovich, Boiling Crisis in Tubes, International Hcat Transfer Conference Paper No. 28, Boulder, Colorado, August 28 - September 1,1961.

5 Bennett, A. W., Collier, J. G., and Incey, P.M.C., Heat Transfer to MLxtures of Hich Precoure Steam and Water in an Annulus, Part II, AERE-R-3804, August 1961.

6.

Burnout Data for Internally Heated Annulus, Power Reactor Technology n. 3,

v. 4, June 1961, p. 22, Table III-5, Colu=bia thiversity Engineering Center.

• /. DeBortoli, et.al., Forced Convecticn Heat Transfer Studies for Water in Bectangular Channels and Found Tube:s at Pressures Above 500 psia, WAPD-188, October 1958.

8.

Zuber, Tribus, and Westvater, The Hydrodynamic Crisis in Pool Boiling of Saturated and Subcoolcd Liquids, International Heat Transfer Conference Paper No. 2'f, Boulder, Colorado, August 28-September 1, 1961.

9 Tippets, F.

E., Critical Heat Flux and Flow Pattem in Characteristics of High Pressure Boiling Water in Ibrced Convection, GEAP-3766, April 1962.

10.

Bray, A.

P., General Electric Internal framorandum, November 1961.

11.

Janssen, Kervinen, and Levy, Single Rod Burnout Tests with Simulated Spacers and Net Steam Generation at 1000 pain, GEAP-3491, July 1960.

2 12.

Levy, S., et.al., Eccentric Eod Bumout at 1000 lbf/in vith Net Steam Generation, to be published in International Journal of Heat and thss Transfer, 1962.

13 Polomik, Invy, and Savochha, Heat Transfer Coefficients with Annular Flow During "Once-Through" Boiling of Water to 100 Per Cent Quality at 800, 1100, and 1400 p=,1, GEAP-3703, Bhy 1961.

14.

Janssen, E., Effect of Instrument Tube on Bumout Limit, Dresden First Load, GEAP-3473, July 1960.

19 Polocik, E.

E., unpublished multirod burnout data,1961.

16. Polomik and Quinn, High Pressure Bhltirod BuLrnout, to be issued.

A "Ch l

g

,OJs N9

's

• Sq

-)

$.Q W

~

Yo

?/

O 4

p

' ' boy %

7

'24 1 o, 3

9 o

'#4

• 4.p,

• 36

%e, q

0 g

• 36 36 e,E

\\

E 4

b, o

eo lb, 3'

6 Y,Q e

t n

g E

q9 3 o

• O l

"#Cb

?g g%

o Og u

• J e

O Po 2,,

G

<40 0+

' do 'N g

'36 Q

• e4 e

4

?o E

E*s, Q

'8 o

'40

?

4

?g E2 h

e 4

e lo 4

4*E+ %

s ' 4, 4 e

'e N '4,, %

'44 e

4

,'o q

o e

h e

+

h, E 23

~

4 e

23 4,

k PDDR BRIGINAL

N/%gg,%.+

s%,,%ys 4

sw

+,9

<4'*

y, '.%,,

+,

gey

?s.&% y,%

"+

r,;-

<s%

'e r e, e

o

?s,O e.o

,'O,

• j s'Es Q,,,,

t 3

o y+

d6 I_

.[ 33- ,

L l

P00R ORIGINAL l

TABLE III APED SPECIAL CHAMIEL BUPROUI DATA,1000 PSIA

• Annulus (3haide surface only heated) 6 D

D L

o/1o Special Ref.

Plotted on 1

g (in. )

(in.)

(in.)

(lb/hr ft )

Featuro No.

FiS.

No.

375

.180 70 1.68 small amulus.

2 27

.875 70 0.14 to 0 56 Iarce annulus.

2 25 540 335 102 0.4 to 1.8 Jacket top end, to 11 25, 26, 27 sirnilate flow condi-tions caused by spacer.

54o 335 102 0.6 to 1.8 Rod eccentric, min.

12 26, 27 Clearance o.61 and 0 96 540 335 102 0.4 to 1.8 Rod sandblasted, 2

25, 26, 27 approx. 300 nicro-inches ms rouchness

.625

.240 40 0.6 to 1.8 "once %rouch" high 13 26, 27 quality boilins experi-cant, 1100 poia.

1211tirod

.250 355 54 0 3 to 1.2 n rce 1/4-inch o.D.

14 25, 26 reds in o.875 I.D.

sing e rod test section, l

0.62 inch min. spacin6 between rods.

.438 52o 18 0 3 to 1.2 Nine rods on o.59 inch 15 25, 26 centers, 2 inch x 2 inch channel 375 520 18 0 5 to 1.14 Nine rods on 0 535 in. 16 25, 26 conters, 1.85 x 1.85 inch channel

• Except for the 1100 psia "oace Brouch" high quality boiling experiment data, Ref. 13 (

I

l TAIIS IV ITALI/JI (CISS) ACD U.S. (UAFD-183) CIECUIAR TUIZ EUBUOUI DATA,~1C00 PSIA-(= 70 3 KG/c:S)

D_

L G/10 Ref.

Plotted on 2

S urce (in. )

(in.)

(1b/hr ft )

No.

Fig.

Ko.

Italian

.2.26 to.390 3 9 to 31.6 0.8 to 1.8 1

28, 29 U. S.

.180 to.305 9 0 to 23 3 0.8 to 1.8 7

28, 29 APED EECTAUGULAR DATA,1033 PSL1 b

B C_

D L

G/lo Special Raf.

Plotted on g

2

.(in.)

(in.)

(in.)

(in. )

(1b/hr f 5 )

Featurc Ho.

Fig. No.

2

.250

.445 41 0 36 to 1.44 cac and both 9

28, 29 surfacca heated 2 -

500

.800 41 0 36 to 1.44 0:e and both 9

28, 29 surfaces heated

_22

'N g ritical Heat Flux C

'N,N*N 8

A Heat Flux Core inlet Outlet

/

/

8

/

/

/

B l

/

y y

Steam Quality

/

l/

I T

Subcooled 48ulk Boiling l

g i

Distance Along Fuel Assembly g

E3 l

FIGURE 1 THERMAL PERFORMANCE OF " HOTTEST CHANNEL" i

g N

l l

.2:=

r-

OOOOOl

\\

\\

r i

)

1 1

l

)

i i

t l

l

\\

l

\\

\\

\\

\\

\\

\\

\\

\\

l

\\

\\

\\

\\

VVVVOV n

o n

n n

ln

)

l l

l l

i l

1 l

l i

n

,n ln n ln n

)

)

\\

\\

)

1 l

nOlOOOO l

l l

l i

l

\\

l l

l FUEL CHANNEL j

UNHEATED NHEAJE0,,1 k

HEATED HEATED CELL (1)

CELL (2)

CELL (3)

POSSIBLE FUEL CELL GEOM ETRIES FIGURE 2 - MULTIROD FUEL ASSEMBLY P00R ORIGINAL

)

i D

D h

t acoa@hil b!g :h e)i g 3' rs

_4y _

U It,t a) i

.g f3-I

(

kh (L

Qi DRESDEN T PE SPddER i

fy;[,1,*

![Rt.

kia 3 - r_._

q.

4 go oi

l;j ~

S l

I

, e _a

- -I to pg

.,; A5J k

s.

i gc.

e 54 L 4.T,. 1 i '.C !

lhd WIRE TYPE SPACER bdURE 3-TYPICAL FUEL ASSEMBLY SPACER P00R ORIGINAL

0 4

e A

0 o

A o

3 2

2 S

T T

E F

B 0

F H

B A

L R L R

e C

I H

H O 0c N

0 I

S P

2 5 0 7 0 0 6

6 0

0 5 0 A

A 3

. 0 1

1 0 0 1

X X

A

=

6 2

5 1

s 0

g 3

Di D P 0

1 TT F F

=

=

00 G

G H

A T

96 G

=

0 N

A E

LL OO L

BB

• D MM E

YY T

SS A

WD 0

E OI 4

LL H

LO OS F

H O

e T

e A

0 C

+

S O

A e

e 3

E F

E F

8 H

2 2

E O ^a C

AI F

F T

T 4

N I

S 8

E P

R L

R 5 h 0

R 0 5 4 3 0 H

H 2

U 3 0 Af G

5

. 01 0

6 F

0 0 I

=

0 0

1 1

g X

X D O P 0

6 2

5 1

o 1

0 1

=

G G

O 4

O.

6 4

8 6

0 O

0 2

f l

% m. E I e'O *

.E a$

Q3 E O3 1

X 2

t""

1.4 i

e i

6 D

DH L

P G/lO SYMBOL 2

(IN)

(lN) (FT)(PSIA)(LB/HRFT )

I.2 0.375.335 6 1000 0.56 O

l.12 A

O 0.540 O.56 6

g 1.12 d

g A

O l.375.370 3.5 1.08 X

1.0 A

o A

X d

A X

A O

Y O

A f

Ng g

'O 5

O

?

U-o 9

E ls O

y

.6 ff j

O d

Tc

.4 O

N O

.2 N

.05 0

.05

.10

.IS

.20

.25

.35

.40

.45 ahs E

hgg 5

FIGURE 5 EFFECT OF HEATED ROD DIAMETER r --

0 4

2 1

h A

5 1

3 6

5 b

O O

H A

O 0

R C

I E

N S

H H

3 T

T P C

C 5

I 7

0 N

N o

0 E

5 F M

I I

3 0 0

. 0

)

0 5

A I

0 6 1

0 3

D 8

5 3

~

C D L P 0

0 I

O t

2 L

=

=

U H

H A

(

G D

D b

RDY O

H 0

g 2

F o

A O

T A

CE FF 5

E 1

A 6

E h

R U

h A

G I

0 F

g 1

A hgA 5

K 0

h

=

U 0

B 4

E h

5 40 4

2 0

8 6

1 l

1

%m O.

x

=" R ae e

ODN Q O E>r-C

6 5

> >4 a

2 5

)

2 MT A

OF I

N 0090 S

R 8

P

)_6 H

4

/

2423 A 1 R

(

~

2 G_\\

.0/

0 T

l B 0

F

(

L 0

H 4

T,

)

(

I

~

4 AS V9 S2 L

4 I

2 O7 DI TU(

0 U N 0

) 5 5

O N 2

4 N9 7

N A DI R

9 8

(

U R B A S

W L

DU 0

0 6

O

)

eN0 4

3 L

EG D

PE l 5 5

F l

AR W

O L

2 3

Y R

E V

T 8

A 2

A TA D

4 S

2 U

L

/

U N

/

NA D

0 N

2 D

E U

T O

A B

EH R

6 Y

E 3

L w

L O

A L

NR E

2 T

\\

I 1

N D

E PA 80 7

E RUG 4

I 0

F O

0 6

4 O.

s.

6

'.O 2

s e

I 2

T 0

u F

8 T

(

H H

coy 3m lp=-

H C

(

?

r

i 4

4 4

0ee>>>44 4aa 2y

)

B r 2

0 L

H 4

A p

MT S

w OF I

N 66600066 6

P R 55524655656

~

• e D

0

/

4 B

a 0

_f~

6 0

L 3

A1

(

4 )

T 4_

I A

8009 28 2

S L N D U 6

(

07 72 00 7

L G o I

1 1 1 s

TU g

M 2

3 S

UN 5

05 5

W

)

ON 2 N 7 1

N A D

I 9

7 O

R

(

8 79 8

L a*d p F

U 2

R B

T 8

A B F

DU R

De ) S 0

0 2

W L L N7 0

4 O

EG H

I 3

5 5

,4 L

(

4 PE T

AR A

D g

A 4

O 2

AT P

o A

G D

o o

O S

g 9 0

LU 8

2 U

N N

W, lf A

D 6

E 1

T D

A N

E U

H O

b >,

Y B

2 L

1 L

R A

E N

W R

E O.

T 1

8 N

0 I

D E

P A

4 X

8 3

E

=

RU G

FI 0

ei h

40 s

9 h

A,f 8

0 2

1 2

8 2

8 4-2 0

0 6

4 s

2 T

o u

B@

T F

f B

R Qew O3m m

e H

m 2

mmm l

a r

l[

?

r e

+

N o e o v v v 4e g

m 6 a

j

[

g k k

E$U"NU2"2 u

g _ ol g ; : _ _ _ _ _ _ _-

o V vd V

V 9

4 e

aS$RRo_$

$E

~

j m'

o Se,o

~

@z V NE*

9 4

=*

= *.

Er

~

d o h h.

f.

M I

o e

g3 z

<=

,e

'4 /j e

O A

• yvv N

2 O

g

\\

U 0, 0 O

G o

,My h

+

3

&'e w

v </

en \\

ol9 a

e';'f f

~

5

'/

o 4

v e T,M

\\2 h

O,'g" ij i

~

m e m e 0 0 a

'~5 5 E

E

/

oso SS

=

6

'/

d n

e e

o -- Y po g

/

c

/

E 2

//

8

/

l)

N O

a o

t N

o-

=

e e-P00R ORIGIN!1

e I I oceave,4,

. m C

N

.J 3 >E 4

2 Z

o m

• G@ mee g

L z

o d ' ' ~ ~ 9 * *' *' *'

/

o V V 1

~~

e Oo V v *J f

9 q>

1. oceu, g

J 4

J g o

e O

-- s i

Okkmoo no if oo s

9 3r Y

~c oce QZ u zu

-es o

8 hee 4

3m2

• e w

m o

O

{

O

.a X

uw

-4 ME N

W f

><o 3

o

/

N 3

x

/

z o

/

N.

W

[

~

V O

3 G W

I e

y

/

O o e

/T

\\

\\ \\g 6

5 f

k4 O

d oo E

f-55 8

o

/ s oo y

cc O /

p of '

o

.g /,

W w x -

o e

t3 w

oo 2

l a

O J J i

G 4 w

o e A c

a / /

G y

a 9

0 e

o 4

l

,8 E<

a e9 N

O e*

A

?

t, y

T N.

o N

e N>

0 e 3

g

@ c

+ -

• 2 Z

v

4 4

2 ooee>53

>w>

T p

2 i-0 I

R W T 4

A S

H O F 4 P

N R2 h

U 22462 4

6 0

/

B 6

0 L

3 0 <

(

A8

~

T,

)

A N 06 69696 D

L I

73 32323 S

~

U

(

S L

2 W

TU 3

O U N

) 05 5

L O N 2 N1 4 9

F N A 0

I 77 9

H R

(

U 2

G B R T

8 I

H A

F 2

DU R

01 ) 50 L

N70 Y

I 35 R

EG H

(

PE E

AR V

4 T

2 A

A TA D

0 2

S ULU N

)

N 8

A 6

xl 1

D E

s T

A N'nO1 2

_~

E 0

H x

f.

Y R

L L

\\x A

F N

8 R

D D 8

E x

N N oN \\

0 T

U U N

OO I

e B B D

p

\\

E

,9 e_

R R P

E E 4

X A

WW 0

II 0

OO E

0 o L L(

R 8a 0 U

G 0

I

> N F

o,, y g

O i

4

,O 4

0 s

g b

h A

h g

\\'

8 0

2 2

t g

t' o.3 0

8 4,

2 8

g W

)

cQg 3

2 T,

0 8 u

r T

0 0

C

+

1 B

R L

l 3

l 1

1 I

APED BURNOUT DATA REGULAR ANNULUS,600 TO 1400 PSIA LB 1.4 0.4 2<

< O.6 R FT2 G

D D2 L

MINOM C

(IN)

(IN )

(IN)

LB/HR FT2 PSIA 1.2 0.540 0.875 102 0.4 TO O.5 600 0

O O.375 0.875 70 0.56 600 0

N O.56 1400 0

1.0 u

o (CD

-a l

O.8 a

a

n, N

O f

sOUNob LOWER o

AT 1000 PSIA g

0.4 ci Cll3 N

q O.2 Ng W

C30 0 02 006 O IO O.14 0.18 0 22 0.26 0.30 0.34 0.38 0.42 0.46

=X E

FIGURE 12 - EFFECTS OF PRESSURE UPON APED INTERNALLY

~

HEATED ANNULUS DATA AT LOW FLOWS g>

r---

6 3

I 04e0a7O I

k 0

A S

A 0000000 P

I P S 0500000 0

P 6466824 2

1 5

1 1 I 3

4 0

2 2

1 A

5 pT T O B y F

lL A

Y T

R O 222222 D

tp L

H T 1

1 1 11 1

I 8

0 I

I 1 1

L L

/

T 0 2 E 7 0

2 1

U 6 A

L 0 N

O l

N S <

R R U E

UL T S

)

2 0

B U L

I 0

4 N W N

N <

1 7

2 I

O l

D

(

E N 2

0 P A DL B

EF A

L 5

5 R

7 7

4 P

A 2 )N Ai L

D I

8 8

4 0

r 6

(

0 0

U 2

N U l

G O i3 e

3 E

4

, f.

0 O

I D

R P E a q*

%d U

0 5

M

)N 4 7

q D i 5 3

E

(

I 0

O M

6 RT 4<

3 0

UA 1

_ N 4

S g

SA ET DA RA fNI O

S 2

PD U

1

\\a P

O 0

F S B

0 O U 0

L R

D E 0 SU a

W 1

8 TN OT 0

CN V

LA 0

EA F

@N e

0 X A

F D O

E E

4

- T g7 3

A 1

E 0

H y

O E

g RU G

d OIa I

A 0

F 4,

0 0

5 h

g g

A h 8

0 s.

6 4

2 O

4 O

O O

O 1

u[ g e

3m

_a i 8s $*

I gs oQO3 Q@-Q"El3r

=-

2 i

I I

I l

1 i

APED BURNOUT DATA REGULAR ANNULUS, 600 TO 1400 PSIA 1.4 O

O l.2 I

HRFT2 HR FT2 O

G DI D2 L

D O (lo 6) NOM Q

D (IN)

(IN)

(lN )

LB / HR FT2 PSIA l.2 G

3 O.375

0. 0.'5 70 1.68 600 0

D I.68 1400 0

m o

0.540 0.875 102 1.26 TO 1.53 600 0

2 U

\\

q 1.0 m e I

~

D O.8 o

8 i

=.

f O 9 0. 6 I

f LOWER BOUND I

AT 1000 PSI A o

Y U

O I

04 I

vu i

O2 O

O N

I O

008 0.04 O

O.04 0.08 0.12 0.16 0.20 0.24 0.28 0.32 0.36 O

ahs _

h e,

~X FIGURE 14 - EFFECTS OF PRESSURE UPON APED INTERNALLY HEATED ANNULUS DATA AT HIGH FLOWS E

llp=

r--

8 2

~

~

~

0 X +

A 00 4

A I

00 2

I S

1 1

~

S P 4 4 0

P YL 0

2 L

AT 0 2

MT A

A4 T

OF 0

N D1 B F

NR 2

R

)H 4 6

,L R

0 E

6 TU S H

o/

TS OU gB NW N L (L

R U 8 I

O l

U N 6

D L B N >

I.

F A

L N 6 6 0

E 3 3 P

D S

I H

ER G O A

P A G

I I

AL U 5 5 NH G

2 4 9 2

O N

1 Y

E D

I 7 9 0

P R

R 0O U

EV E

0O R

0 U 8

U T D

5 5 0

S A iN I

O0 0

SE A R TA P

D A

4 D

X I

N S 0

F S

+

U P 0

• O U O

L X

7 B 0 S

x 0

T U

+

R 0

C N E

E N 1

W 0

F A X

O T F

L A EDE

\\

- T 4

5 A 0

1 E

)

0 H

E X

R s

+

h gU f

G A h I

8 0

F q

0

+

2

+

1 6

4 2

0 8

6 4

2 O

O 1

l 1

O O

0 O

N 4 o9 2

2i oo C o

• I E2

=C%

3-@ ZMP Klll

C A

}

I

~

6 T

0aj A

0 M e, A.6 8 C I

,,l

j* i7

+ ?. 5

/

. s w. =

M.

)

G A

?

l K

aM 3 09 Aa t

U 0 L 7 3

%y4

~.

I O =

2 44 Y

T C

(

MT N) 50

(

A OF OS 5

8 M

5 L

A I

N t

7. t OO 7

R 0V A

P E H ER t,1 S

gJ

=

Q 2

TT U

S.

O r'O/ T U

04 m.

O

.8 U

t B O l

fi

1!

4 M

O g\\

C 37 L

8 O

(

N A

).

B

(

(

E T

E S

)

2 0

6 7,

iN r

S S U L N H

4l t.

l

4 I

I 9

9 2

I L

(

2 1

4 i

'[

4 G

C U

(

H

~

N N

N T

~

A

)

3 5

2 A

I A

2N 5 2

0 L

DI A

A D

(

5 9

T

~

0 A

E t

'l T

)

5 8

0 s7;-.

4 D

• w.

A R

iN7 0

),

E DI R

1 5-A E H

(

3 1

3 L

U E Y

)

J 6

N A L H

(

A I

A I

w 2'$a.y 3

N L

S A

A T

B H N M

R S

I A

I R

R U

E T E B

L H

RI T

I O

2 T

N O

'\\$%

s B

I (C

3 H

A

\\

'l W-O X

S c

W h

e A

U-8 T

2, A

\\

g*g -

D D

E N

P 4

A 2

a1."

F O

T '-}.

7~"

NO S

0 2

I R

A E

P S

v M

u R

O v

L u

C T

u C

6 N

u; o,

4 6

b' g

A i A I

N T

j M U E

o,o O

R ER u

U

,A H

G

,.t oe c,R c E,N ;2 I

F u

i 0

o e,E r, T t

R oA O

g M

8 t

0

g 6

aa 0

^

4 0

2 8

t l

< <g O

i O

0 8

6 2

0 8

o 2

I 8

e t

2 T

u o

F 461 B

T 8 0 R

H

(

3-NODoDcM C:,C:

lr llI l

i?

l.

l l 5

d

/

HORIZONTAL LIMIT LINE x

l-8 E

a

=

STEAM QUALITY FIGURE 17 - EFFECT OF FLOW INSTABILITY ON " BURNOUT " HE AT FLUX i

P00R ORIGINAL l

i

O

.,.. - -.a..

. _. m...

, n...-

... _. w

. -..1 n. 6..,1 =....u,. ; _,_

4 2,... r

. I. s., a.~..+,--

_. - n.- -.-.-

. y..

g..

...~..s.,.. ~...

.4...-

.. D..,.

...m

+

..n

.... w.

~.. - -....

p..,.

,L.,,,_

I).t

.t. +tt' +

4.x,.,. _. O. h.

.l. iF..,

. 1 r...

. 1.,..

.g.

. 40..@

.4

. g

.o

... p~_....~

4, s

%~

4_ c

y.. %.,_

s..,m

.o-W.. e.+T.+, Ti.w

..p. 1..

.m

. J..

m.. m.. m.,.,

w u.

3.

. p,..

....H.

.w i.,

o %.4o

.p r o.

O..

- w

-- ~

= -: n a.- ur. -

. =.

L.,

m 2..,

. y Q) ~n..= -.

1. . o n.==.: (

'~' i ~'O

.X'~o,X'X ;. 2 p

....z,

=v o.

, =

. +.-

3

. O._;. nn.. m

.e m., :.=.=u..._= :=_

_20

. ~

2 A.

.o..

.J..o..~,.-....,.

q

.,.,.,._- -.... _....-q

.,,. M..

..g Q

<p r.....-..

f,t

. f...

u_ y

-.O....-.,D.

...o..

.g

.m

. r...

o

. 44.

..u...

4....

g,,,.3, 9:. 4....

w, 4.

.4.,,

q

.m _. u,.

g..,

~, _

.<4 <

,.,%r o.., e,.,,m.

_ w w W. -....w.--,-

.4 MiA

-41

. a a_.

f.

. -.J.

4.-e 1.Q,

g g..J

.g3 -q. g g D

HJW g %

0.

26Q$ 8[d4 tE:-i:M 4;

k..

.i ch

- F

.- Mi ff.

i=E O

~EM =T:

.n- =

n n:-a+=

v r_.i:G--

' r"7E

'hJ W I=

29-r n-O w.

= =

.w.:==

.._...e._..

. y.

w g

O

_ y..

N

_ u.

.. o..

. _c...~

., c

_... ~ _. ~..

. ' ~.. ~

'O tij O o.,

3-

..O m. p_.,-.

e.

4g

.. g..

x CD e

.... e

.,.. p

~..

o

. ~,

m qw

4. Q:...o.

m._....~e...--

_m _...

p..

...42 u

J

. -..F. 4.u.1a._

p.

g

..-4--.

.I.-

.4 O

4 L_,.,....a._...e o

. +, - -,

b

.-.D.

g g

..p 4.,.

.,y &. e_

r. 7...

.O, gD, r.>.,0 I

4 -3

. ~..

N O

4 7

.. 4. A.

11. O

..a.

.w. a....

t m

. 3. -.

.r.i Oo

.%_~ -H._,.H. I.r-&._-Ft

,?..

o O U i.ii i6 e. ei

..]

2g Y..;.'.i

• • "., '.1 M '

. m,4t..

• * ^ '. - _ ~ - '... _ - * ~ '

- *.. * * ~. *.

+

• W '_"+'

,.l*'

4...

sn

^

+.

a.J

""". U #

4y--

P' p

..4_

]

k.

b _+*.

_. <... +

.g

.+

y.

. +...

q -

d...-_.,

h 7

-.+..., + -...

.. ~..

e

~e..

Z

_.o.+

.+

_o.

o r -.. _ _..Q _ _....,.

o

.4 f- -..

., +.

..++,3.

r.

., +...

w..

.,. +

. o,

.m 4+

+4

+

.++

.n.

g

.++:

w g

= r:.~: L;

_....--- - - m h O u:=:=.=:===.

=2

=tm-

-==

~:,

=

~

u.: ;

.: m.. =

.

-.. a==-:

..

- :~:~ n::

.: r c: :

lij

n-

- ~. :-

- - d nn ::

.=

n.::

n :-.

. : t -- ;..::l:..

.-.y.....=

.=:

=~

n-- ~n : -y

_..: 4..

= :..

=2 g

.-_u==.-

]

..u..... ~...

g

~

~

.1. l-

. a.4 4

. w_.--._..

II.

4

,s 4 -

4 W

~.,.

44.

,t

. i.

.4,.4u4.+,-..*4_...._._3,..

.3,.,

.+ +

e

.-..e.,..

..u..

.i..

,J W *,.

4. _.,.

4

.i,j

. l. 4.

. w -+.w.-.. %. % _,~.p4 4.J.- iajl e.

. H i

..%++.

. i.

t

,1 },,

+ %.+ +W-d- -. --

ei, I i 4

h++

+

1 Ii i. l.

.+

+-4 J- + -.4 1 - ! - {.

lI l'.f

• +++e.*++

m.

zu a,, l: 1 Ay,

=.

. =.2 ;m L i,

i.;

r* m:0 4

.n

.r

-l

==:=n==nu 2: ar m.

72.y1'. i ' a '!';; o p

,.i!

l,,'

L F

i!'l

.I ie 3:'**.L.?*.*M

• M p'R****.5. u_r..n....

i.

i,

nn.n.m...n..n. n.:.n.-.

n... i 1

4 n

,7 l

.. +..

...4...

i l.I 9

{ ;,

i,

.4

.4.

4

+.

e. '

1 i,

., 4 4

+

4

.e,.e +..i.4.,iI.. I.

1...+.. 4 i

I

.4,.

's

~..

l

]r*******-

• * - + * * * -

+

a N

O.

O.

c.

O.

e.

e.

e.

m.

m N

~

~""

P00R ORIGINAL

8 4

2 T

~

4 F

4 R

H F

/

O 0 0 8 BL 4 0 0 S

0 6

E 5 5 I

R I O O 6

4 V T M

A UI O O O I

O CL T T T S T P

DT" EU 5 5 9 0 I

3 6

D O 7 3 2 0

~ ~~

N N 3 3 0 4 E R I

MU O O H c

MB T

E G

O N

V 2

C E E 6 R

E A.

L R 10 3

U R

AI I

D U w

~;~I~

I C

D D. E S /

T S W T

D D A E O M

O Y E R L 8

I R H H P F L

- ^

2

~T U

O N

R I%W I

4 U

2 B

"D E

F I

0 D

2 O

Q 1

M 2

9 e

E 6

R s

N 1

U G

FI o

N e.

e.

O x

\\

e

\\

Mx lil 0

8 x

4 7

!i I

l Ii 0

N N

O e

4 o

6

\\.

j i

2 U T 3B F

T R

C w@.

H 2

,s:ec

[(

r

A.,

l..

'N h

-.44 x

4

,s etsr rir rOR o

.245 etsi rir rOR o. 335 s

w~i x^

/

n.

m

~

/

A PREDICTED rOR Ogs.495 a

<e; p.

N PREDICTtD FOR DH=.375 a

.6 APED BURNOUT DATA Y

( HP BTU K

FT2 /

0, Dr Du L

10' i

.4

- llN.)

(IM ) (IN ) (IN ) (LB/HR rf l

.500

.745.245 36 2.0 0

.500

.995.495 36 2.0 e

.2

.375

.780.335 70 0.56 a

T

.375 1.250.075 TO O.56 A

c::s 1

I I

I l

Q

'O O2 04

.06 D8

.10

.32

.14

.16

.38

.20

.22

.24

.26 28

.30

.32 lll23 x

3 FIGURE 20 EFFECTS OF HYDRAULIC DIAMETER IN ANNULAR GEOMETRY O

,Xl3 llm=

r-

I.4 1.2 l.O s &

BEST FIT A

\\

FOR Du = 0.445 PREDICTED 10 FOR Du = 0.800

.6 APED BURNOUT DATA g

G_.

HEATER 2

\\

( HR FT )

CHANNEL Du L

106 THICKNESS 2

4

- (IN. X IN.)

(IN.) (IN.) (LB/HR FT ) (IN.)

\\

1/4 X 2 445 41

.72

.010 A

g

.2 t/2 X 2

.800 4i

.72

.010 A

C N

I i

1 i

i i

O O

.04

.08

.12

.16

.20

.24

.28

.32

.36

.40 44

.48 FIGURE 21 EFFECTS OF HYDRAULIC DIAMETERIN RECTANGULR CHANNEL r--

8 4

4 l

i 4

S F

R E

O 0

B T

S 4

O 2

E E

5 I

T 0

M V T A

R I O

F 4

I M

D

)

UI O O

AI R

D E

C CL T T S H I

T P /

L DT O "

B U

E U "5 N 9 0 L 6

A M.._

DO 7 2 0 3

R NN 3 S 0

D ER A H 1

6 Y

MU O T

0 G

H

(

MB D

N O

E E

2 C

. L E 6 3

S R O 3

A E

. A D U l

E R

AI D.

z _,

D I

E S /

R T S W C

D D A E O T_+

IN O Y E R L 8

R H H P F T

%l-2 ASW "5

S O E L 0

VF R

=

s 4

UW m

X D

1 2

COL T

I D

MNA IL 0

"T 2

U

\\

5 O

7 \\

N

\\0

~.-

R UB 6

1 D

\\'

I h

E I

F "0

\\

D N

0 \\

O

\\

1' 2

M 1

s 22

'~

E R

U l

I8"5 l 1\\

8 G

0 I

2.\\

1

\\

F N

N

\\

s t

iB h

4 0

g

\\

\\

(

I lIt' O

6 0

a~

6 2

O 4

2 t

i s

2

[-

E

?

_ E T 2y ON Ell2-

= -

l

C l

r

8 4

S WO L

4 F

4 M

U F

I O

D 0

E S

4 2

M E

5 8

T 0

R I O

0 F

4 D

VT 1

A N

M

)

D A

UI O O

I R

E CL T T S H R

T P

/

E DT O "

B E U "5 N 9 0 L 6

T 4-3 E

DO 7 2

0 S

M NN 3 0

ER A H 1

2 IA MU O

(

T 1

~

D G

MB N

C O

E 2

I C

E 6 L

E

. L 3

U R O D U l

A R

I Al E S /

R A

D D. T S W D

=s D D A E O Y

O Y E R L H

8 R H H P F 2

DES A

E R

C 4

N 2

I T

A S

5 E

0 0

V 2

R

=

U g

C D

T I

M I

6 L

"5 1

7 T

O U

O N

R 2

U "0

t.

B 0

D E

\\

I F

I 8

D "5

0 O

\\

1 3

2 M

\\

2

\\

E 4

R N

N 0

U G

I F

0 6

4 1

0 4

2 0

2 I

8 1

2 T

0 '

U F

8 T

4

'B R

H Om. % OmE3r e

m m

a

8 4

SW O

L 4

F 4

H G

I F

H O

0 S

S 4

2 S

"8 T

0 R

E 5

R I O 0

F 4

E VT 1

A T

)

M D

UI O O

I R

E E

S H M

CL T T

T P /

A DT O

B I

E U "5 N

"9 0 L 6

D 3

DO 7 2 0 C

NN 3 S 0

(

g I

MU O T

1 8

A H L

ER U

G MB A

N O

R E

2 D

E 6 C

L

=

3 Y

E

. A D U I

A R O H

R l

D E S /

D I

D

. T S W E

D D A E O S

O Y E R L 8

A R H H P F 2

E a-RC N

T Q_

A 4

X 2

S E

V R

U z

C 0

2 IT M

LI

( :_

"T "5

U s

6 O

0N N 5

N

=

R n

"5 UB

\\D 7

"D sO "O s 2

E t

3 1

I O.

ID F

\\l s'

2 M

O sl

\\

( -

4 8

2

\\

\\

\\

0 E

x R

N

\\

U

\\

G

\\,\\

I s

4 F

g 0

\\

s

\\

O f

2 0

8 4

2 0

6 l

1 1'

j 4

2 T

0 6

U F

8 0

T 4

1 B

R H

NQse,g%m@" ::p=-

(

r

I I

I I

I I

I I

APED BURNOUT DATA AL 0 PSIA

_1 I8 1<06 10" HRfT2 ANNULUS D

02 L g

INOM es

( BN) (IN) (lN) (LB/HR FT2 )*

pSgA I

s

.____]____.._

l S AND BLASTED

.540.875 102 4 TO.6 5000 JACKET

.540.875 102

.4 TO.6 ts 4000 MULTIRC D l

I THREC Robi- ~~

.250 54

.3 TC.6 D

1000 l

t l

NINE RODS

.438 18

.3 TO.6 N

1000 2

--+----7 i NINE RODS

.375 18 0.56 O

ICCO i4c0 l

l l

1 I

i i

1 e

n j

-r j

t- -

i 4

3 l

,_-z i

e 5-j i

, _ _ _ _ _ ~, _. _ _ _. _ _ __ _.

_ ~ __

-.-__-.I_-__-.4-..

• S4 0

i g

..__.,..i

,,e.

1

--.._m 0

o;.

n I

4l y_ Q_gl

_ _ -_.q _ __.

j

_ _b __ b I

4 n _. _

,h

. RECOMMENDED REACTOR g,"

"i f

. LIMIT CURVE AT G = O 6 xlO6

{

M

... ___..____i__ __ __ !

[_

~___'.__..___I I

[____.;___.

i i

l C3 l

i i

l U

2 08 04 0

04

.06

.t2

.16

.20

.24 28

.32 36 40 44 N

1 Ah c

X g

5{

FIGURE 25 COMPARISON OF

• BURNOUT" LIMIT CURVES WITH APED SPECI AL CHANNEL DATA AT LOW FLOWS r==

00 00 04 1

1 4

I N t> + 4MO e 4

2

+

M T

OF N R 5

!227 2 2.4 I

)

B Nll

<<l1 4

I 0

H J

/

l 1

4

( L(

A

$220 488

)

I N E004 S

2 l I

! 11 511 6

I P

T

(

3 b

NYS555 F

)

OB 2

776 S

AOL 0

I 888 W

T O R

(

O AD I

H L

b005 085 g

2 F

I T S 2 D,

)

N 442 537 c

I N556 5

M U L l

(

243 E

U O

I N NN D

A 16g N

M R

o E

U H 8

I B

C

+

2 T

A C H

II P

g N

2 k

)

4 A

DL T

EA F

A A

P I

R N

I 8

S j

TA E

D 4

I P 6 O

N O

b 2

S 0 S

L Df l

U O

E U

E(

L N

U T*

SS N

b SU DD NA

, bd, AR OO N'I N

H h

J 2

LH RR 0

I A

T g

g C

N BT E

E DE EEE 6

L kN O

A kCNC RNN Rl I

kAAN HI I

Ox C

kJS0 TNN T 2 E

C l.

P A o 6

S

\\

E G 1

e R

D T

E 4

DA P

ED E A

N V ER 2

H MU 6

T x

M C I

W OT CI S

EM E

RI V

L 8

R 0

U 1Y C

T MI I

L 4

X 0

TU 7

O N

R U

B 0

"FO NO S

4 I

R 0

AP M

5 gO h

f C 6

h s

6 c

2 E

R U

G I

2 F

1 6

2 0

6 4

1 8

i 1

I 2

T F

B R

H N-@M r

4 4

+y 04>> +

2 4,

T L

0 S

}

F 2

W 4

AI R

MT

++

O S

H O F L

8 F

N P

R68885 4

H H

8 1

I l l 1 G

0 l

B 6

H

/

I 00 <

L 3

T

(

A1 A

T

)

A A

02220 4

T S

L N L 16 I

70004 A

D

(

1 1 1 2

D E

c TN 3

L UN E

)

55555 OA <

2 N

N57776 NH D

I 58888 N

RC

(

A U

2 H

T 6

C B L 8 F

)

A 50005 2

L I

L DC R

Og N7 4442 A

EE H

I 35556 I

(

C 4

PP E

AS P

R S

2 A

4 2

D I

E

)

L A

E C

I P

S A

P N

H N

8 x

I EI 0

0 T

CM 0

2 W

A1 1

S R 6 D(

{

E A0 E

T "U V

E, A H R

S R L

C 6

U CI s

1 C

S R

L T U

TT B T

L L NE E

I U L EK D C M

N A CCN N IL N MCAA A S E J S *O 2

6 T

6 U

4

\\"

R0 O

O1 N

,CTX R

U A8 8

8 EI

\\

R=

0 G

F U

D O

T E A N

D D

NE O

EV S

0 MR 4

X IR M U 0

A C

O P

EMI

= W CT RIL 0

l-

+ 'U G

I 4

F 0

hA 8

0 2

1 2

s g

2 O.

e.

6 0

6 4,

t s

0 2

T o 8 u

F T

B 0

,:QCm N m

=--

(

1 B

R H

".r

9~

O 0

6 L

o03*$++uM aa 3

+

c,

.a

%841 6

)

Q 2 222222222 22 1 r!

S A

MT l 1 e l 1 I I I i l

I p

T OF o

A N

OOOOOOOOO OO D

)I R TTTTTTTTT TT H

GM B 4

/ 888888888 88 O

g 2

S eT'+ $

W B

[ \\ (L 0 0 0 0 0 0 0 0 0 009g e'

a 5

+

cEm" IU a

O

)

) 243956766 3

4 L

O L N F

P t 61 83 1 1 3 1 1 93 4

M

( 4 3 33 33 W

4 2

2 A

+3 0

8 O6 m

9 4

D

(

l557583868 T(2 2. g. 22331 e S 0,*

E A

DN009042925 a

M I

I. 3

^

T S.

N.

88688 g

A 6

a U

U EO4821 3

4 A

MN55$568034 8

6 4

T E

a n-e A

)

L N

A ag

$e D

E E

A S

I S*

I L

a a

O E

L C

A a

B U

(

T 0

N I

"N A

J I

4 L

A

^

t IL o

A V

A t

a a

A T

e e I

• e a

6 R

j*

a 3

E H

T O

e a

H T

2 3

l w

S E

V k

o a' R

U 8

k. @

m C

2 e

c T

MI o

I L

O 4

d' T

r 2

U O

a O

N RU B

l o e 0

• 2 F

\\

O 2

2 T

T

^

e NO F F S

R s

o I

t H H i

/

6 R

I i

1 A

/ /

6 P

B B a

RO M

L L L a

O I X

T O

E

/C NG 6 a

2 C

N O O Al

^

I E a 2

8 A

tX X

I H

R 9

2 G

C 2 2 P

E E 7 7

T.

a N

f R

R D

A 0 O N E U

o E V G

L U H H I

I G C C

M R 8

F U

N N N M

0 T

1 4I N

C A

1 I

OCT 4

C EI E X X

R MI R 2 2 L

4 I

D X X

0 E 2 4

P t

1

/ /

A O

2 0

t 8

e 2

o.

6 6

2 8

6 4

2 2

8 e

2 T

u F

o '0 T

B 1

B R

TQN mO r-

+

H

0 lI, t

I '

4 i

6

+

I) 003*

w + '. ; a

• a e*

f L

M 9

8 5

C

's J et 899e

?.

881 A

t 4

)

/

T S i

1 1 t t

P

-. O 30a DW 8-

. O3i e '

'T T7 r J

3 mT T T T 7 Y l OJ

/

2 222

.d222222222 2

87 (Lt i e

t 1 6 4

8 6 t f f

@4 G

S

)D(

) 2439567 66 6S3 3 -

4 W

u if O

AI

( 6 t

83 1

1 3t 1

9

'l 23 PA a

3 33 33 4 2 S

2 3

4 L

(P

) 557583868 O 07 6

• s

- 4 _ f.

l" 8

F w

4 H

N IG S0 T ( 221 22331 8 S 880 0

DN009042925

4. 4 A

i I

1 4 3 H

0 4

3 8E.

EO482i88 a

. P[' I,

T U1 N

A y

4 A

E f

ll 44 MNS55S68 4

T

. * [t T

I

'pe-g T_

~

(

A B

L N

A D

)U 1

E E

A S

E S

L B

L U -

P4i g

4 I

n B

CR G

0 A

(A I

li'

'l 8

T L

NL U

3 A

AILC q

VA AR R

TI O

IC E

6 H

!{'

l' l

,4 3

T o

O o

H T

G I

,O W

2 3

SE VRU C

A o

o 8

T 2

I g

M IL T

e U

4 O

2 N

y RU F

^

m 0

O a

2 N

l o*

e a

O S

2 2 I

T T R

F F A

P R R H H 6

M t.

O l

/ /

8 8 6

C L L a

Rd 6 6 Ot 9

X 2

T OO

/C 8 I

X A

l E

X I

a 2

R E

l 4 4 s

G 1

U R

G R 4 4 a

D I

A A

1, I.

oo EE F

L HH D V U C C o

NR G HN1 MC 0

E U 8

N 8

l A 1

1 o

3 M

T 4 4 T

OI C X X o

C M E 2 2 E

R xX R IL D 2 4 4

E / /

0 l P 1

t A

O 8

6, 4

2 O

e 6

4 2

O e

s 8

s 2

=-

m 3r T

u F

'0 0

T 8

1 B

R H

(

_