ML20008E648

Best Estimate Post-Test Prediction for Loft Nuclear Experiment L3-6

ML20008E648
Person / Time
Site:	Yankee Rowe, Maine Yankee
Issue date:	03/03/1981
From:	Husain A, Loomis J, Schor L YANKEE ATOMIC ELECTRIC CO.
To:
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ML20008E641	List: ML20008E640 ML20008E648
References
NUDOCS 8103090330
Download: ML20008E648 (70)

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{{#Wiki_filter:. s (]' TNfS DOCUMENT CONTAINS L 900R QUALITY PAGES \\ BEST ESTIMATE POST 'IEST PREDICTION FOR LOFT NUCLEAR EXPERIMENT L3-6 by LILIANE SCHOR JAMES LOOMIS AUSAF HUSAIN 6 iS10309 0 3hk

Cc ~ Table of Contents Page List of Figures 2 List of Tables 4 1.0 Introduction 5 2.0 Model Description for RELAP4/ Mod 3 6 2.1 Calcula tion Overview ' 6 2.2 Blowdown Model 6 3.0 Comparison of Experimental Results in the RELAP4/ Mod 3 8 Pos t Tes t Calculation 3.1 Pressure 9 3.2 Differential Pressure 9 3.3 Fluid Temperature 9 3.4 Density 10 3.5 Mass Flow Rate 10 3.6 Liquid Mass in the Sys tem 10 3.7 Liquid Levels 10 4.0 Re f erence 12 5.0 Appendix A 55 r 1 L

( s a List of Figures Page Figure 1. RELAP 4 LOFT Nodalization 16 Figure 2. Intact Loop Hot Leg Pressure (0 - 200 see) 17 Figure 3. Pressurizer Pressure (0 - 200 see) 18 Figure 4. Pressure in Downcomer (0 - 200 sec) 19 Figure 5. Pressure in Broken Loop Cold Leg (0 - 200 sec) 20 Figure 6. Pressure in Broken Loop Hot Leg (0 - 200 see) 21 Figure 7. Pressure in Steam Generator Dome (0 - 200 sec) 22 Figure 8. Density in Broken Loop Cold Leg (0 - 200 see) 23 Figure 9. Density in Broken Loop Hot Leg (0 - 200 sec) 24 Figure 10. Density in Intact Loop Hot Leg (0 - 200 see) 25 Figure 11. Density in Intact Loop Cold Leg (0 - 200 sec) 26 Figure 12. Density at Steam Generator Exit Intact Loop (0 - 200 sec) 27 Figure 13. Differential Pressure Across P,ips (0 - 200 sec) 28 Figure 14. Differential Pressure Across Steam Generator (0 - 200 sec) 29 Figure 15. Differential Pressure Across Reactor Vessel (0 - 200 sec) 30 Figure 16. Temperature in Intact Loop Hot Leg (0 - 200 sec) 31 Figure 17. Temperature at Inlet and Outlet Plenums in Steam 32 Generator, Intact Loop (0 - 200 see) Figure 18. Level in Pressurizer (0 - 200 sec) 33 Figure 19. Intact Loop Hot Leg Pressure (0 - 2400 see) 34 Figure 20. Pressurizer Pressure (0 - 2400 sec) 35 Figure 21. Pressure in Downcomer (0 - 2400 sec) 36 Figure 22. Pressure in Broken Loop Cold Leg (0 - 2400 sec) 37 Figure 23. Pressure in Broken Loop Hot Leg (0 - 2400 sec) 38 Figure 24. Pressure in Steam Generator Dome (0 - 2400 see) 39 Figure 25. Density in Broken Loop Cold Leg (0 - 2400 see) 40 Figure 26. Density in Broken Loop Hot Leg (0 - 2400 sec) 41 Figure 27. Density in Intact Loop Hot Leg (0 - 2400 sec) 42 Figure 28. Density in Intact Loop Cold Leg (0 - 2400 sec) 43 2 W-

( List of Figures Page Figure 29. Differential Pressure Across Steam Generator (0 - 2400 see) 44 Figure 30. Differential Prer,sure Across Reactor Vessel (0 - 2400 see) 45 Figure 31. Differential Pressure Across Pumps (0 -2400 see) 46 Figure 32. Liquid Level in Core (0 - 2400 ecc) 47 Figure 33. Liquid Mass in Reactor vessel (0 - 2400 sec) 48 Figure 34. Liquid Mass in Steam Generator, Primary Side (0 - 2400 sec) 49 Figure 35. Liquid Mass in Hot and Cold Leg, Intact Loop (0 - 2400 sec) 50 Figure 36. Liquid Mass in Broken Loop (0 - 2400 sec) 51 Figure 37. Temperature in Intact Loop Hot Leg (0 - 2400 see) 52 Figure 38. Temperature at Inlet and Outlet Plenums in Steam Generator 53 (0 - 2400 sec) t Figure 39. Break Flow (0 - 2400 sec) 54 3 1

List of Tables Page . Table 1 _ REIAP4 Blowdown Sys tem Model Description 13 Table 2 Initial Conditions for LOCE L3-6' Table 3 Chronology of Events Experimental Data Versus 15 Test Prediction 4

9 6 BEST ESTIMATE POST TEST PREDICTION FOR LOFT NUCLEAR EXPERIMENT L3-6 1.0 Introduction This document contains the Yankee Atomic Electric Company post test prediction of the coupled system thermal-hydraulic response for the Loss of Fluid Test (LOFT) System during Loss of Coolant Experiment (LOCE) L3-6. The RELAP4/ Mod 3[1] and RELAPS/ Mod [2] computer codes were used to calculate the thermal-hydraulic behavior in the LOFT system during LOCE L3-6. The analytical models used to perform this prediction should be recognized as "bes t es timate" predictive mechanisms. 5 l l

2.0 Model Description for RELAP4/ Mod 3 2.1 Calcula tional Overview The code used for the post test analysis presented in this section of the report is RELAP4/ Mod 3 version YAEC-05B. Two update changes were made to the code; one to represent the behavior of the LOFT steam flow control valve in the secondary side of the steam generator, another to allow the use of different contraction coefficients for subcooled and two phase critical flow. A listing of the input description and update diagrams is given in Appendix A. 2.2 Blowdown Model The RELAP4/ Mod 3 LOFT system model used to calculate blowdown during LOCE L3-6 is described in this section. A schematic of the LOFT system is given in Figure 1. The model used for LOCE L3-6 is a modification of the EG&G LOFT L3-1 model (Re ference 3). The following changes were made to the base nodalization (Reference 3) for this analysis: 1. The break location was moved from the broken loop cold leg to the intact loop cold leg and the new break spool piece was modeled. 2. The accumulator was removed. 3. Primary coolant injection flows were added to properly account for the system mass inventory. 6

~ 4. For modeling two-phase degradation behavior, data that describe the pump two-phase head and torque characteristics are needed. The new LOFT head and torque multipliers based on experimetnal data, presented by EG6G in Reference 4 has been used. 5. A new volume (33) representing the pipe which connects the steam generator secondary steam dome to the steam relief valve was added to the nodalization of the steam generator secondary. Complete phase separation was used in this volume. 6. Two junctions (45 and 43) instead of one were used to represent th e feedwa ter inlet and the auxiliary feedwa ter inlet, respectively. 7. Six junctions were used to model the leak through the steam flow relief valve; one before the valve cycled (junction 41) and a combination of 5 valves and 5 trips throughout the remainder of the transient. 8. High pressure injection system (HPSI) location was moved from the intact cold leg into the downcomer. 9. Only one volume was used to represent the core. A bypass volume representing 5% of the total core flow was added to the reactor vessel. 10. Phase separation was removed from all volumes except reactor vessel v ol ume s, pressurizer and s team generator secondary. 11. The critical flow models specified for the junctions were the Henry Fauske model for the subcooled region and Moody model for the two phase region. Mul tipliers of 1.0 and 0.6 were applied for subcooled and sa tura ted break flow, respectively. 7

A briaf d2ccription of each control volume is given in Table 1. In specifying the system initial conditions, i.e., pressure, temperature, flow an d powe r, the actual initial conditions of the LOFT facility at the test initiation were input to RELAP4 model within the bounds of measurement error and heat balance consistency (5). A list of measured versus RELAP4 initial conditions are given in Table 2. 3.0 Comparison of Experimental Results in the RELAP4/ Mode 3 Post Test Calculations. This section presents comparisons between the experimental data provided by EG&G (Reference 6) and the post test predictions calcula ted by RELAP4. Short term (0 to 200 sec) and long term (0 to 2400 sec) results are presented. The selection of the parameters provided in this report was based on the availability and quality of the data, the correspondence between modeled volumes and physical locations of measurements, and the overall importance of the parameter in assessing the capability of th RELAP4 code. Some results are presented without comparison with expermiental data when those data were unavailable. Table 3 presents neasured versus predicted (RELAP4) sequence of events for experiment L3-6. 3.1 Pressure Comparison between calculated versus measured LOFT pressures are presented in Figures 2 through 7 for short-term plots (0 - 200 sec) and in Figures 19 through 24 for long term plots (0-2400 sec). 8

Good cgreement io cchiaved batwetn the calcula ted pressure in the primary system and the measured one up to 945 seconds. After 945 seconds, RELAP4 under predicts the data. At 1300 seconds, RELAP 4 predicts a 30 psia repressurization of the system. This is due to a change in break flow and break quality. Following the repressurization, the pressure in the primary system drops again until it reaches 330 psia at 2031.5 seconds. In the secondary side of the steam generator, by carefully monitoring the leak through the s team relief valve, good agreement is achieved until 945 seconds. At 945 seconds, the pressure in the secondary side of the steam genera tor exceeds the primary sys tem pressure. In the LOFT experiment, th e two systems become decoupled at this point while in the RELAP4 calculation, the secondary pressure follows the primary pressure. 3.2 Differential Pressure Differential pressures across core, pump, and steam generator intact loop are presented in Figures 13 through 15 for short (0 - 200 see) and in Figures 29 through 31 for long term (0 - 2400 see) results. 3.3 Fluid Temperature Temperatures in intact loop hot leg and temperatures in the steam genera tor inlet and outlet plenums are presented in Figures 16 and 17. The LOFT system reached saturation at the cold leg at 40 seconds while RELAP4 predicted saturation in the cold leg at 90 seconds in the transient. Af ter reaching sa turation, RELAP4 predicted the LOFT data well until 945 s e c ond s. The temperatures are underpredicted (Figures 37 and 38) af ter 945 seconds and seem to follow the pressure prediction response. 9 i i

4 3.4 Density Densities in broken loop cold and hot legs and intact loop cold and hot legs are presented in Figures 9 through 12 for short term (0 - 200 see) and in Figures 25 through 28 for long term (0 - 2400 sec) response. Good agreement with data is achieved. 3.5 Mass Flow Rate The comparison between calculated versus measured break flow is presented in Figure 39. The RELAP4 results are within the measurement error band. 3.6 Liquid Mass in the System Four plots for liquid mass in the reactor vessel (Figure 33), liquid mass in steam generator primary side (Figure 34), liquid mass in hot and cold leg, intact loop (Figure 35), and liquid mass in broken loop (Figure 36) are presen t ed. Since data on LOFT liquid mass inventory are not available, no comparisons to the data have been made. 3.7 Liquid Levels Level in the pressurizer is presented in Figure 18. RELAP4 calcula ted a delay of 3 seconds in emptying the pressurizer. This may have been caused by an initial lower level in the 10FT pressurizer as compared to the value used in the RELAP4 calculations. The level in the core is presented in Figure 32. Again, data are not available but the LOFT instruments did not measure core uncovery. RELAP4 calculates uncovery of the core at 1300 seconds, recovery at 1500 seconds and finally uncovers again at 1550 seconds. 10

We are using Wilson bubble rise in the core. It seems that a homogeneous 'model in the core may have been more appropriate for the case,where main coolant pumps are still available. This assumption would not have shown core uncovery, ins tead would show high voiding of the core. 11 f

4.0 Re ferences 1. Yankee Atomic Electric Company WREM based PWR-ECCS Evaluation Model (version VAEC-058), YAEC 1160, July 1978. 2. Victor H. Ranson et al, RELAPS/ MOD 1 Code Manual (DRAFT) 3. W. H. Grush and M. S. Shiuko, Best Es tima te Prediction for LOFT Nuclear Experiments L3-1, EGG-LOFT-5033, November 1979 4. EG&G presentation to NRC on January 15,1981 (RELAP 5 Calculations of L3-5 and L3-6) 5. Glenn E. McCreery, Quick-Look Report on LOFT Nuclear Experiments L3-6/L8-1, EGG-LOFT-5318, December 1980 6. LOFT L3-6 Data Tapes 12

Table 1. RELAP4 Blowdown System Model Description Control Volume Description 1 Nuclear Core 2 Core Bypass 3 Steam generator secondary s team dome 4&5 Upper Plenum 6&7 Intact loop hot leg 8 & 13 Steam generator inlet plenum and outlet plenum 9 & 12 Straight section of steam generator tubes 10 & 11 Curved sections of steam generator tubes 14 Steam genera tor outlet piping 15 Piping leading to the tee preceding the coolant pumps. 16 Piping from tee to primary coolant pumps 17 Primary coolant pumps 18 & 19 Intact loop cold leg 20 Upper annulus at the vessel inlet 21 Downc omer 22 Lower plenum 23 & 24 Broken loop cold leg 25,26,27 & 28 Broken loop hot leg 29 & 30 Reflood assist bypass piping 31 Pressurizer surge line 32 Pressurizer 33 Piping connecting the steam generator secondary steam dome to the s team relie f valve 34 ECC injection line 35 Steam generator secondary downconer 36 Steam generator secondary shroud region 37 Con tainme nt i 13 l l

4 Table 2. Initial Conditions for LOCE L3-6 Input Value Parameter Measured Vatue for RELAP 4 Primary Coolant System Mass flow 3.8+0.05 3.8 6 rate (x 10 lba/hr ) Hot leg pressure (psia) 215.67+20.3 2156.62 Cold leg temperature ( F) 544. 5 + 2. 0 544.5 Hot leg temperature ( F) 579.1+3.2 579.5 Primary coolant pump 1.55+0.25 1.55 injection flow (gpm) Reactor Vessel Power level (HW) 50+1 50 Steam Genera tor Secondary Side Water level (in) 8.7 1.2 8.7 1 Water temperature ( F) 517.4+1.4 507.0 Pressure (ps ia) 807.86+8.7 809.27 Mass Flow Rate (Ibm /sec) 61.3+0.2 61.3 Pressurizer Pressure (psia) 2161.07 36.26 2155.11 1 Liquid level (in) 46.51 3 46.5 4 ECCS Initiation pressure (psia) 1778.17+20.31 1778.7 14

Table 3. Chronology of Events - Experimental Data Versus Test Predictions Sequence of Events for LOCE L3-6 TIME AFTER LOCE INITIATION MEASURED PREDICTION EVENT DATA DATA (seconds) Reactor scrammed -5.8+0.2 -5.8 LOCE initiated 0.0 0.0 HPSI "A" tripped on 3.6-0.2 2.2 Pressurizer emptied 20.2-0.2 23.9 Upper Plenum fluid satured 28.5 0.2 30.0 1 Intact loop hot leg voiding initiated 29.4 5.0 30.0 1 Intact loop cold leg voiding initiated 31.4+5.0 90.0 End of subcooled break flow 44. 2+ 0. 2 90.0 Steam generator secondary auxiliary feed pump started 73.410.2 73.4 Steam generator secondary steam contrei valve opened 88.8+0.2 88.7 Steam generator secondary steam control valve closed 99.6+0.2 101.2 Primary sys tem pressure became less than secondary system pressure 930.0+30.0 940.0 Steam generator secondary auxiliary feed pump shut down 1856.0+5.0 1856.0 Primary coolant pumps tripped off 2371.4 2031.5 15

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. o .c nr c. a E e I _a ra e T O a m e. a a o C S o . c w .a . oc 2 w t., I en p4 a :;- A t .e. oc i g-8 @C o.a.e ua o., u 4 L [- r-EMN n :. a oc o c. 0 t - 6a w :x:. i N y -' Rm mC r 4 w v; a r 5 c. is - Qd ed 49 W M o u a w M e a H w t^ s'e 3 . r* w J0 t-3.- 3 .e W.1 t e ,__1,_ r_,,, ,y, ,j, ,g, a c",r r etcr esti cess cui ,03i est cer 049 6 d9 (91GJJ 3Nnt';38e 031 10H dCG1 1'J01N1 34 p = 4 o O O 63 'l' 'I' 'l 'l- .g. ,i, ~ 4 I M 89 = dk ~_ = a .a. r.- - fd - 4 a e b I _' o FJ 4 4 I g K cr r T O o s e e-e o M $3 2 /, 07 O v3 :' Q G e e-J = k M* De = mu g-o r. o b ,,: _ N W m 7 - a w E bj ~ G%C w o~- .s a u o 3 k at U" g, 0C W N 7 H N y.3 L b W *le 1 -- t u c-3C C8

1. w eV m

N m n. LD a 1 4 4 4 N 1 4 S L e e I ~ O r4 x 'l

o m _., r r r = :.mt,-

1.----

es z coc: csti cesi ce,21

ci e st.

ces ed 20 as (91';a; asnss38a b3718nssasa ,35 O O (' '3 'l' .g. ' l' .y. 'i' "8-Ce . P r, g e Ps 9 -6 ?; a e ^J =.=ti t w O 4 r j. 4 ~ t T 7 I e c / ~ I C N sy b g ~ C' - o2 ] Q G e, l hm j ~ uu i; 4. @G l L T '. - ' N # 2 I y o ) r :. 4 l'.n % .' ~ 5 $g4 0

w. T g

w-~ t 4 0.t. w .J [ M 1 w c m uyo ~- J k ~, ~ mw i t 3 Ifj w ~ h C a. A i. a.; M t f i I b,, t. f +) 4 4 n h n 4 r .4 a d s [ ^ i* .n. A A I, a, 1 esn - 0., 05;l C t?"' ' C%:n e-, 054 Cc-ng ~~' '~ '6 US I91Cd, 8 J g g 3..-#'~Na 3BDSq3ya 36 0 0 5 .~ . ~ .~ T g 2 a a g o g si 3 g u g r g G ,u S o. i 2 t l 2 g g g g g c, g g 0 0 i l 2 g 0 g g g g g g 6 g 3 g G g i L g 5 r l 7 g 1 A T 3 F g D O g L 3 3 g O g ") e T g G, L i g N g 1 d Oc g O lo S.. g C g I a T ) Rn" g G 1 2 os pc g 2 oe h t g S L P-s 4 g 2 C. e 0 M, t g rn0 O, P 3 1 S ue4 C-i A g f gk2 L 3 i o E 3 EFr R a 1 B 4 a 0 i t 0 P-e 0 n( R.. i 0 i T l g 1 e E a r R a s a u S g s 3 e r A G P 1 i l 7 5 L a a a a a a a a A 5 i G a a 1 a a a a a a G S i l 2 a h e a 2 M a a a es T ,.6 ,$V ocor oo - o0-a0-o .U,,- o o'L $[E J J sr ( mN (.G _ a v n. - ow oJou GooJ Zd z w Ta's a w c r_ ) ) L r wa r n L3 g ~. r. . L.

r. r C

r. ,.c t. c l c a y \\ .o n .a oc o z.. t r3 e4 es u a. 3 _ O o x V_

a. n O U 6

en o o LT N,a in E t* ~ ~.

a. :..

,s G CO u o,c r w ax OC O N j I t

k. 80 1

-w c: v ca -.c Ce e w o e w 5 =m e if a 4 o , =. h F + - / r t 5 I a d J _-s R I? \\ t

• w.

L. .T. .i. .i. .i. i 0;T; 0 '.c z est i co' i esci 0;;i est cc-eQ i W uS 1919d) 931 10H dG07 f.3P0b9 Ni 3@rM 3bd u L3-6 ret F4 COMD6RISON T O D A T fs .t,,,, 2 to o s s ,,,.. :,,,., m.. - .e. O re.im (J w - y. - g- - g- - y-g- i o o. c_ (I oo QO O N c_ D w w ro l. 0 04 o o LOFT L3-6 k-aco $N \\ 0 E N,. z_ Tao.. wo O '- r w cr o

o O"

Owx RELAP 4 C o O o P("C*4 cs ,a a a a 1. a i Ii an m) tua a a aaa Ia Ia m L.LA bd &.1 L.A.Al ^ ' ' ' ' t* a D) rso ,Gr s. i c 0 ", 1250 '5G? I 750 ?300 2.'53 25GO a a a a a ' l^* T i t1E r M f,1 TI O Figure 24 Pressure in Steam Generator Dome (0 1, 2400 sec) ---. m- -w-

---

a w

--s w +y- -eer--v--- --m-w-wwwr----W

---

W-e-v----p-----w-'

e= r-we--w-+ w--

---

T*-w=-s*-w-rs---m

-+

~, 2 l 5', 8 i 2 i h 4 4 f l P 'n i T P A V R D O g T e L N. C d 2 0-lo s,, I C I 1 e ) 9,, I 5 oePe p 2 os p, i L M c, e 0 O, rn0 ue4 C, gk2 [ i o 4 t Frf B 'l P. 0 T A. n( i t E y R t is S ( n e 3 4 D 3 3 L P [ r AL p E w R lg I w /' .t w Il !lggE1< I ' sm l ') 1 a } a ve .s ~ , ~ ,? >T. ,~_- 1 3~ Ov or-(# o. 7 n .17,1 1 r~ rC ot "t W os-O.o" o c) >- 7w<oYU =- n~ L L J rr (

• O

r c, Og og 0.7 . or ~> at c. s 7 a E

o t'

e. C s-C w .o O .a O u H I', O a m Za

n. -

O' ou O-ej$ n co Q" - . n-eu.o o c. . e a 3

• 4 7

L. r. on g N b E E' ., 'O i; A I O Q co O *- ____= x-i

• • w w

m , _E c.3 T x e, C '* 3 Md 2 3 a r.

f. W 2

2 r N[f-g. .r'- i j .iigin 3 m

• f

_ 2 t "MP.c ~ 5 Y .r. .i.. .t. .t. .l 3' .i. CL 09 OG Ot CE 02 01 0

U S2 85J (E23/81) 931 10H dCC7 N39Cb9 N1 111CN7C 41

L 3 -S REl A"4 COMrhRIS9N TO DATA =te ro c: t u ai n -ret. :: n.22 t e,,, 3,, .c e. i a, g. ,y. .t. .v. f n l 5 CS ~ D S i 1 00 i S S 1 E2 ~ yl E 4 un d fi ~ l f{ RELAP 4 ' I,,I j l z l ? ~

1. }

IDFT L3-6

I l:

~ i t N1 M ** J' /........ l cC T5G ir/> 1 'n 225G 2SGG j TIME f 5t r.1 Ti 0 Figure 27 Density in Intact Loop Hot Leg (0 - 2400 sec)

l L3-S RELAP4 COMPARISON TO DATA tort ts_. on McTen st *Pr. '9 t /D.' '?7. ? ?. M ',*. ettm*e ser i o t l l l a o l r-e ~ l o- <r ev, n ~ s u-L._ N as -n on .f.; w I a . \\a. .j o b J L t o i o [ u RELAP 4 o i a Wo tr o l s t z i w [ r", I4FT L3-6 Il ~ 7 l o l l p o_ T ,li I g:r-. .t. ..u m t...,_, m mt..... m a m m,,,3 ..i. m. (C 7 5 '., "0 s c,; e,' ', U i

r.,

.' 3 c, nc,, T l t1E ' 51~ f.1 TT i: Figure 28 Density in Intact Loop Cold Leg (n - %nn ..c) q

i iII 1 O G ~ . 2 5 3e .i s. i - e G i I S e t n 2 2 I ,l r.a u G A I P. V 6 4 R 3 P D L A L T O F; 4 E T R S I W ss N. G o O,.. ls r

u. ' D c

G. A I R L l r e o )e r I r t A. 9 u o s a. 3 0,. i N. 1 2 r I ( e s i-r- e n e n 1 [ r n S r e C f g P u G n. n i n l 4e r EF a a-i M e t tn r i '/ I n i An I

h. l i

r p S T e l r E 1 e R f f L f i 6 D L I l. y! im G, 7 l..d ), f' . 7' l f i ,.w f l f . e 5 I l \\ ,I t /, [ 'e I J G 5 l a 2 I m n .t .f tg' r oe 9 o= O" 0 O g 5 O *h 2 c n" a ce 7wo r67 $ox.r 3,wI 4 mL t " a a aA ll

e k O ,,g, , g, . g, ,g, ,g, ,g, [ P. t. Ps 9 a J. a Ve rs =* a W W r a g e F 4 C a 2 O I e 6-A m m 4' d 0 k A u

• =

9 4 c,; l _ C' g. q G-a w k G u n3 m G Q"

• an W

a a m m d, m G k ^ ** ~ G e-3 y O E' ~ u o *- 4-i kA wa ON a 6 u w* " ..g.en u 8 au m en . W y U GQ p-- 4 Il CMw b'. i J 4 G Js C.. k

=

H G W H. %d O' .a e W h- ) ~ H 4 e i-a i F j l'pt. - a J.' 4 ., C 2 a )d - - er:1 Tf %=f 1 3 i u 2 m a a fi 1 ei a l2 .1m a I. .Ia ,i1,,,, ,,,j. ,g[ C#e 00; 0;' ' 0; CLI 00: c '. t 0"- a I ob ! Ol'3d 1 13CC2A 3013b30 CCOU39 0C3%

• 3 ilC 45

l Og .i. Et .? -1 e o-s' r. u' G d f -- U.. c. 1 J 4 h 4* C F 4

• C T

j e o n a, 4 a a u a ~ Q M 3x 2* '-) o-w I G UG ~ e: ~ cg ao-6. c.. 4 3o a,s y eo El yeo a-~ r o; g&N a s. ya I .A 8 6* m_ w n 'l - m y o G i.' .3

• 1*

^ u u e 4T W ] e 9 l c m a ~-{ .A ) >v' fp.5_g- ~ 'ide- ; I g;- h' 1 -- eg,. _r_-_- m d.I a 3 5 1 ~ E f 1 >>1-1. .i. .i. .i. .i. 3 1 s>> C5 05 0* CE C' 't et-r., ;* ' Ll d6 (SjCd1 SdWnd CG083S JUDG0382 JjjC 4 46

F e 4 O 'l' ' l' ' 3-1 g- , g. ca = 9 O e 4

• O w

e A . ea - re p 4 k C m - e = _0 . a. e n m G ~ o - o W O g. - V e Q *n = G 0 ?, w Q C.. O^ w-e ~.o g r,: - o, a e. . a m I-P e4 W b' WQ p > ~3 F* w y 0N .Mg E ey y l A .m O e. . Q 3w ~ t y C) 0 _.a 3 L G ~ b a L( r~ n 4 (* 6? V M M 9 %J D, q. f6e h We ^ ^ - I- -l2 .l. .]. , j, ,j, ,g, b L 5 5 t ,e I 9~ I lW IAJ) 13 A 31 3801 X ] W 47

rg ! ri"4 I 0F '.I 3,6 ME%URED VRI dEG ~ w....o..,,.. . r v c 3.,.

2.,c ai :a

.c . m . i, oo o ~ oo = y 1 e r 1 >.x n .o o 7

• a.

1 \\ ed 1 I Z o o a3 e. t t C3 .3 c3 o a. \\ .~a O I w) J tJ O s? ed ~ i y h RELAP 4 o l= Ia I-a lm g* asaaagLa a a a a a a a a a a a a a a a a a aa a Ia s uaaal-Ia ?u , s ", .sa i c"n,

• .' w t.3",
• 75G

'.W.

22S3 253", a a a a a m (i Ia a a a a a a a a a a a a a a a a a a a I T i tif fM'I i Figure 33

l Liquid Mass in Reactor Vessel (0 - 2400 sec)

,-m, <.~.-..-,--,-,e_-,-e.. ,---r--<-~-ww

RELRP4 L OF T L 3 -6,;y,E AS,URED VALUES M o Plates ytogg 392343 jry.aspg ge sp-gg,, pg, .o. - i. i. - i. i. w ..4 ,,,,, gg f Oa 4 e FJ 4 r 2 ol ow i >q rJ go 6-z ts2>o zo O ca oo a r o O O C3 s 3-j C3 ,i e o oo 6-re w-e. id z ta o o ta g OS .AJ P, RELAP 4 i s o i o, .a..k .i. .....u..i. <C 2% 7,

55 s cy; s ;,0 s,Or;

, ;.,3 2.y, ,p a yg T i rif, f $[.I I Figure 34 Liquid Mass in Steam Generator, Primary Side (0 - 2400 see) w e N wewv*- wwe wa sur vuurvw w ww- "'Cv'+W-ww-'1.-*-rT1-'v

• 'N+-'

w w w'e' v'w D'-"1 w=* -"'-"-'P W -V+=-w-' -V W*-T--%V7-+vw".wu'vw--W-'r-v#"v*m*wTw-7me s't-Y'WW-N'W ew--1 %+-"m'w-w'W-m--w'v'www-'ww-w C w--

e o i- ..i. ..I, 'g' ,g. a .N k ~ o y r a fd S a. r i 4 to , o w '.3 K 2 T> O ac 3 w e MA - 0 D~ 5 (1) '* m Cd 0 w-n u 5 u E,: a m, e. ' o w, e5 8g t. s. n ua a

c. -

g e khU O* w 4 .E. e.U " "{ E s& l@ sd e 8 .s e*o h' ,o a w o d 1 U E 5 w C '5 1 L ..v 1 d i W I .a o j w -.e ~ ce P

R*

o 8 - t. c G tw t 00ht ,i. ^ ^,^ ^ 0060

coy, nCC,

,on,s i 00 8 006 CCt 6 w S WM A801N3ANI GGSW 010011 G310703 ONS 104 l 50 L- -

l ,a 1 l t O O .i. 3 _g m L. ~ o .o A. r2 ra 3 y

S a

r. ) .= 1 L7 N I w e J G> ? i Q w (' o. e, --) ~ g co., a C. c w-en eu r_ v o ,e "o t - - 33 m w-g r. o

• 1

,co u *" g m-w o _y r oc'[. m I F e ezo w- ~ - t,'. e o ~ m . Y 'g n ..er L A C oo w r-e a.s M 3 .o o n r' a-o f ~ .i. .i. .J. .r. .i. .i. .i. .i. DC?L 0000 CCr2 0C00 0061 002: 006 00F i 52 WM A801N3ANI GGSu 010017 dG01 N39Cb9 51

L3-6 RELAP4 COMPARISON TO DATR weu.ea ser.. w t on r u m s. ii..i. o. =ure ior o its 7 t l I o, @ k t'6 !{ e o g ai L oo U [4 o r LOFT L3-6

n. o

~ c3 o RELAP 4 O Oa .- o .z e z I ono _ o _ -t:na. o ,........s.........s... .....i.................i........,i................,i............... Z 250 ,S: 75G 1c00 I?50 1500 175G 20 % r25G 2500 TIME ' St.r 1 TI O Figure 37 Temperature in Intact Loop Hot Leg (0 - 2400 sec)

l ,],., (,f h9,N TO DGTG =t. v e,i ,,,n,, .t. s i c, c2 c i-i- i- . q,,,. I <s L f c' w. i / - k.: ,p e w=._ ~ LOFT L3-6 D z, 7-wO J 'a g RELAP 4 w a C

• ,n_

c3 o., u, w a 7 r d s te.J () -.s v z* i '] o o =c, .: - in ~c L ~ Mr' /t' ~ o t a b o, l88t PL o ' m mu t u t-d l-ful-l 1. Et 2% 1. sa irsa i r. 3. i 15U 2.rv, 22SG TSGG tit 1[ ' - [ I, 3 i[ f v Figure 38 Temperature at Inlet and Outlet Plenums in Steam Generator (0 - 2400 see)

O., 'i' i- ,i, o te K r. a . a r, .a

• J ca F

4 L.. 3 <. L4 1 ? ~ Y kJ

• a e-J 4-a O

~ z, - N e. o-aa a-j ^ c-q u cI d R$% n a-4 ':: t r-

• r

="8 ol u, o u-b- EU N g S G TT% } .m y[

r. i' "

= z r- "e' m o t m w. ,.c' e_ 4 b, - -w c p-y- L' 77 y. 2 4 e, ja aC a ? S 'A a m 4 r a 1 E 4 1 s t, S - ') 3 1 J () r4 4 t _., - _, _ _. _ - _ _ _ _ 7- )b-- - ) ._.J _. C' '> E ct s, O., si 9 EE MP t')lg/yglJ 31Sb M013 MS3b9 1 54

r a e 5.0 APPENDIX A l l 55

r i ! a cc CuMt ] 010 Lb7227 'of CULT.31 e 7 3 ,OADT,VAvPUS cc CuML j. DIO LS7226 cu COML.175 LENGTH ( J I:(5*m a x Jt,Nt 3) NLFL T +R

• M A x,tur.*NL IN T cc FLUS ulu UHLS

~" 01 FLOS.339 IF(I.NE.49) GU TU 85 uADTu a o.uS C .i C IN THt Ft1LLualNG CANOS [HE LOGIC in THIP THE SPtLIAL STEAN u u C VALvt IS IMPLEMtHitD C . n IF(TRIPf5,XXXX)) GO TH 999 n (su Ill NH6 999 IF(DADT.IT.O.O.ANu.P(h).bE.930.) navi =o.O , n IF(P(nj.LE.92u.u) DADT = -DAUTO AP(PLK).GE.1030.OJ DADT 30ADTO IF(P(M).LE.1020.0.AND.DADT.GT.u.0) DAUT a 0.0 j. VAVPOS VAVPOSt0ADT*DT APtVAVPUS.LI.u.uJ vANPus 0.9 IF ( V AVPs es.GT. I.U ) V

• VPils : 1. ')

a Boo VALCUF =.366455* vAvviis**3.24oo43.wavpiis**2+.151757* vAvPoS-00041633 n 1F(VAVPOS.LT.O.1) VALCOF : 00o43*vAvPOS+.UltS7 3. IF(VAvPOS.LT.0.plo) VALC0F : 7293g*V4VPOS Ar L V Ab Ds )S. L t. u. u l V ALLisF : 0.0 IF(P(k).GE.400.) *P(I) = val.CoF*P(w) p. IF (P ( n ).t T.4 09. ) dP(I) z 1.tuo*valroF*Si1PT(P(A)**2-(20:1.)**p) .i L5UUALI) : ZLNG ~' FSUhh(I) = -UNEEX7 g. ~GO TO 270 55 bUhl1 Nut 01 HJa!.237 p. 3 ,DADT,VAVPOS =4 AnJu.e57 0ADTzu.0 p VAVPOS=0.646934 e4 Luta.31 3 ,0ADT,vavPUS p c0 CuML.175 . bENb l N ( J ) 3 t s *WA AJ UN+ 3 J

• NLP L I t d
• M A x,JUN 4 NL IN I m

p

• b PLU3 p.

cl0ENT NCH 01 FLOS.434 AAJ B 1.0 n. 08 FLOS.440 I ,w.,. ' :.,,. ' D s AA1 a at' .i u au rLua.4ui,FLOS.442 w1HPIN = -AAt*AJeLEAK(H,PLL,1,UER,TC Hi>x, t T PL T alHMAX = AAl*AJ8LEantH,PLx,T,utR,gtHisk,TTdkT i u l a lC h 56

r e f i e t 8 i l I I i l i a a 4 i l g t l i s i j i i s i i .= i a w o. e u .1 .J a. + 4 s =. s. s s i u. c. .n 4. i m. s s + 1 w - "t c.. i w u I ~ .s i e o =...4 s 1 w 1 m.

e. 3=

e a o 2 c, i w - -, e o. .s s 7 a. 2 4,., 3 o e. c, e x = - I i 1 i e l i l i I I l. i i I l ll l >I 57 , i, _.,,,_, 1_, !,, = ' l. ~. .......=1

1 1 : 1 :=1 aa = u a ini 1 =;1_O, vrr m 1 18 W

G G G G S 9 4 4 4 9 9 8 4 e e e e e e 9

LISTING OF Ihrst? Data FHW Cask 1 () I natoa-tusLu=o etasoxa.t-equas a-sT44=-ww -ease.ce->=ouu, A Coat-Ltem-6 2 elenot =2 9 9 in 37 e 2 52 l 10 1 5 to 8 5 3 0 e ( () 3 0190nP 58.0 1.0 -844*: O 5 020000 am a ap 3 Ja as Ju 3' Ja el JC 39 Jw af Ju 39 aP 19 T IM E sYee oaTa "Sw&4^ 2 l# 9 ^!! ".*?* E,4 4 01007e 2 10 2 0 O 05 0.0v02 a.0 () a 9 03003n 2 10 2 0 0.10 0.001 2#.0 ^Me-5 !=" ,"Sa ^ 9ast

• • 4 ll 030ngn 2

100 299 0 0.n01 0.U00na Sa.,30.5 () " 12 030nen 5 10 1 0 0;ea l 0.001 "&sef>----2 St 3 9 1.961 e2.0 cr le 03008n 80 100 50 0 e.ncl 0.00004 43.0 () " 15 300ee 2, e to 2 0 Oll0O 0.00na 3000.0 0 gm e a n a e 3 17 ge0nin 1 1 0 S 0.0 030 eEND () " 14 0e007a 2 1 0 0 7e.2 0.0 e3faNT aus FEEDwafte 't-- 0auste_ -1! a a

5. a--a,0- -_a p E a"

~ 0.0 esfaeT PEEDws?"' 80 Osonen 4 1 0 0 0,0 () " 21 CaOn5n 5 1 0 0 0.0 U.0 e8TEaN FLU" a 22 man.e. e as a m . s3. m_a .avns er

surn

1. 3 Os007n 7

=4 6 0 1778.17 0.0 eMPIS C) - 2e Seve.n 12 1 0 0 n.n v.1 .sCHaa 21. osuosa__la___t a a n+9 n;a an*TIONaL_aufAm 26 Osot0n e =4 6 0 330.0 0.0 ofwIm pu=ps () " 27 Geolin 3 4 33 e 1910.5 e.o eCLOSE STEaw CONTE 0L VALVE Lean a __ aa nacia. a a a a enn_a a.a enerN asan 5 W9 Geolga 9 1 0 e ee.o 0.0 e87aWT COOLaw? INJECTION 70 palmaev Pumps C) 30 Geoten 13 e 33 0 1o80.5 les e sfauf attum0 Lkan los 11 Osulsn is a tu a tala.% tae a_3TA21_3ECU5D_LkaR_e06 38 Osolen 15 a 33 0 1010.5 l** e Sfawi sECOND (kaN 301 () " 33 Osotto le 4 33 e 10ln.5 13.0 e sfast arCUhD LEAK 2ns is naaga. et a su a tain t n.e . afAgr asenNu Laan tas 35 e C)- 3e volu=E uava 17 e = 38 te5UbeLE IwuEsefeIP TNDICATOs DevDLU"E na7A WEfe! EVAL () 39 av0L.w 80 FwtSRl8et TE*P GUAL P

• WE eE8ENTS

= ma c5Ga!* 2 0 8113 E2h 'I t0"' r

1. 1 usonpt 20 2175 nan 550 584.50 oli eCout Myrass

() 4 e2 osgest a9 407.57953 el.0 0 e8G 6LC aftsw 00"E 93 d590e* 2_2

1. 1s9.fa737tja 5 L9,5 0

-t: mELLNUM AWUVE_ FULL em 050agt 20 2167;66495 599.50 et. owuf LkG UPPkN PLkNUM () " e5 vgonet 00 Pl56.421eo 979.50 el.

• ! L M L 96 uSgare ae ris2 anq573 519.50 at:
• T t_ HL wLRlWRI - - -
• ?

090nat 0 0 2183.e1722 590.50 el.

• gG INLET PLL"U"

() " as 95Un9s 0 0 21en.3295n Se1.87a0 el.

• SG Tuets INLET 05V1a*

O O 2137.203t1 %55.009h_ sir

• 59-TUNL8 50 050111 v0 2139.71en2 5e9.1660 =1 esG T HES

() U 51 05v121 00 2 3%.57782 5e5.310000 =1 esk TUNES OUTLET 92 csug3 a a

1. 13 h.12131 5aa.Su

=t; esE_cu1Ltt_ptthup 53 0%0 tat 0 0 212a.2eMm9 50s.iu =l. of L C L ()

• Se egot%t 0 0 2121.9g7t2 Sea.50

=1 et LLL " --___ 55 _- 05Vint_.._ 0 9 2116.790092 599.50 el! ePu"P INLLT.... 34 b50179 0 0 2152.17899 See.59 el.

• etaClue COULaNT Pun #

() 57 ogggat 0 0 7tme 7ad?% 54a.50 el.' eeuwp OUTLLI 9e u5939* Q0 D18L.k14h5a S e u.5 a =1 . I ;L_L. L.__ t 59 0%v70s d u dl77.anneen S e e. 5.s el, awy INLFT ANNULU5 7 0 2'7*.a M70v go.9n et, .ww UD=Ntuhtw ^~ --~-

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