evaluation of melcor code using phebus fpt0 test
TRANSCRIPT
KAERI/TR-751/96 KR9600282
PHEBUS FPT0^H9§ 0|§o|- MELCOR 3E Evaluation of MELCOR Code Using PHEBUS FPTO Test
1996ti 9H
y ^ 1 XI- S) g f ^Korea Atomic Energy Research Institute
0| MHA-il 7|#M3A^ %)l##L|Ck
*R: Phebus FPTO o\g& MELCOR 3E ^71-Evaluation of MELCOR Code Using Phebus FPTO Test
1996ti 91
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4
SUMMARY
This report presents the analysis results of the PHEBUS FPTO experiment using
MELCOR1.8.3. for the core degradation process, the fission product release in
the circuits.
The objectives of this study are to assess the models associated with the core
damage and fission product behavior and to identify the phenomena, which
have not been modeled, or area where the model could be improved.
The calculation results were much improved by performing the sensitivity studies
for the three phenomena, which were considered important to simulate the test
scenario. The first case is to consider whether the debris formation is to be
allowed or not. The second case is to consider whether the oxide layer can hold
up the molten mixture or not and the third case is to consider the number of
nodalization for the U cube in the SG and the vertical pipe at core exit, where the
gas temperature was changed rapidly during the transient. The MELCOR code
well predicted the thermal/hydraulic conditions in the core and in the circuit for
the case of the intact core geometry, but molten pool in the lower parts (20-
35cm) could not be formed in this study because the mass of the relocated
molten fuel was negligible due to highly oxidized cladding and also the relocated
rubble debris was modeled assuming no decay heat considering only ‘9’ days of
irradiation.
5
The dissolved mass of U02 was calculated to be negligible because it was
calculated using a simple model based on the existing molten Zr at the instant of
candling start. Therefore, an evaluation of eutectic model is needed to calculate
mechanistically for this case. The total mass of H2 generation was
underpredicted because the stiffner was not modeled and the liner inside the
shroud could not be considered during the oxidation in MELCOR.
The some difficulties in modeling the activation product were resolved by
manipulating the RN input associated with the initial fission product inventory.
In MELCOR, there is no model that can simulate the release of Ag, In, Cd from
the control rod but from the fuel during the fission reaction. Therefore, it is
considered that the release model from the control rod should be implemented
into the MELCOR.
The fission product release from the core was calculated using the CORSOR-
Booth model for the low bumup fuel. But it was not well predicted because the
CORSOR model was developed based on the high burn-up fuel. However, the
calculated release fractions were very similar to the measured values.
The MELCOR code has many options for user controlled parameters, which can
give a flexible modeling capability for the various types of phenomena to the
user. But the selection of the parameters and options should be made based on
the sound understanding of the phenomenal knowledge.
6
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an 30 Ru n-t MS ----------------------------------------------------------------------------------- 47
an 31 Xe n1"# MS ----------------------------------------------------------------------------------- 48
an 32 Sn (In, Ag )&# MS ----------------------------------------------------------------------- 48
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NEXT PAGE(S) left BLANK
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Ollg ECU ##S| gg E#0||Ai #g£|g !g gullol ON2 2|g driving core
0||A| Xl|0|E|g 5i|gl SW0|EK E# 0| ##S| gg2| #0| S^EgO] &X\ 9#W
ZAN%7| EHgOll #g£|g g2|«g gA|#%CK s# Af-gg q^Ego] 7|°| fresh
ggSPI EHgOll gap w##g 0.0 EE ^g#ggg Wf
30
81444 oil# 34s 7H94S4. #994 gxm #83 9914
*01*21 #499 ttHSoii 9#9£ gqi^c). S7|XHH1*0|| 44 81E *UI4$5i4.
7119 S4S #944 ti|H, 844 34 94^124^ 9# 391 1a|-4?I|
0||=484. 0|8 CORSOR 2lO| JL<&± #°450|| 44 x^i 7155. 7H^£|%7|
48014.
Hlag ##8 #9454 XIIojsH Class2 (Cs), Calss3 (Ba), Class4 (I), ClassS
(Te), ClassS (Ru), Class? (Mo, Co), ClassS (Ce, Zr), Class'! 2 (In, Ag, Sn) 'EM
ti|H484. ## 7114 u|H, 843 o||go|4. *9454 44 S?Hb Cadarache
<gB±#44 8*115 44 442# 49*14 3991 b|h, *i|A|4%4. ru 3° 4
15,000 0|^ 4497KE! E98E5 944 #94 54 9#8#o| 44@7|. E|%ck
MELCOR 5E8 §0|A*2A| 391 4 48 4342 #94 9911 A|-SA#
AWI^WI b43 ^ $iE# #84 Bis 5842 $14. 344 0138 E14
94014 0H7H9434 498 494914 44 #84 o|sH4 45t ##$#
9442 3# 39#o# 34. ^4 E44 452# 494 31 a|§^ 3°o||8
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31
1. I.Shepherd, L.Herranz etc, “Pre-Test calculation for the Thermal-hydraulic Tests
carried out in the PHEBUS-FP Containment Vessel" JRC, 1994.
2. A. Amaud, L. Cordron etc, “PHEBUS FP Test Specification FPTO + FPT1",
Cadarache, Sept 1991.
3. MELCOR 1.8.3 Reference Manual and User’s Guide, Vol 1-4, SNL, July 1994.
4. R. Gonzalez, P. Chatelard, F.Jacq, “ ICARE2 Version2 ModO Description of Physical
Models”, IPSN Note Technique DRS/SEMAR 92/24,1992.
5. L.J. Siefken, “Liquefaction Flow Solidification Model For SC DAP", EGG-CDD-5708,
Dec 1981.
6. H.M Chung, “Material Interactions Accompanying Degraded Core Accident", ANL,
March 1981
7. Measured data Tape from Cadarache
8. “PHEBUS PF FPTO Test Preliminary Report and Compilation of figures”, JRC, May
1994.
32
Steam Generator U tube into‘3’ CV
Horizontal O pipe
Vertical pipe into ‘4" CV0 point
Shroud
1 PHEBUSFPTO ^ '••I'M 21-
Low Plenum
Source
Horizontal Y pipe Horizontal C pipeWet Condenser
FPTO shroud configuration in the experiment
10-ZrFPTO shroud configuration A in the calculation
2 Shroud f
33
J.m 4 60cm »Ii>l
uK1-5f shroud (C
ASE1 / CASE2)
Outside Shroud Temperatures at 60cm (103K)7S >2
O O O O O —» ^ —* -* —& f\j
OM^OIOOONIA. 0)030
3.% 3 M
M^ (C
ASE t / CASE2)
Cumulative H2 Production (10'kg)> m 22ooooooooooO—*Mo^-xcno>>uootoo
*?] 6 /| w
- (CASE2 / C
AS
OOOOO — —
Vapor Temperature in SG U tube down side (103K)
ON)^Cn00C3M-NC7>00O
(eh
svd
/zhsv
d)^
3^
s fez
:
OOOO o ^ ^ ^ » hJ
Vapor Temperature in Vertical pipe(t03K)
OM^aiOOOM-^OOOOT-#—r&
TIME (I0
3s)
I 8 4^4 60 cm 4 'I ring ^14%
>].£ (C
ASE3 / C
ASE
UiC
> The second ring cladding temperature at 60.0cm ( X 1 cT3 2
OOOO—» —• — KJhONJCMO<zl0)<ON3Cn00 —
7 (C
ASE3 / CASE4)
Cumulative H2 Production (lO-lKg)7S>
Inle
t tempe
ratu
re (10
3K)
5 Central CR ab
sorb
er Te
mpe
ratu
res a
t 70cm
(103K
) TCL
TSSTC14: unreliable
9 °1 70cm ^IH iH!‘ring >1^- (CASE4)
Low Plenum
inlet T
KAERI
10 -V-tl y-?-5r f (CASE4)
37
y 12
60 cm °1M
ring «)?!&-«- £E >|-£ (C
ASE4)
W
> 3R Fuel Rod Temperatures at 60cm (103K)2oooo—»hoK)ro(^4ocHC7>tOhoaiOD —
TIME (103s)
11 4 = °1 60 cm °1M -T-y^ ring tai
<95.-g £E 7^-i- (CA
SE4)
OOOO—• — — |sjroK>W
> 2R Fuel Rod Temperatures at 60cm (103K)
OUOIIOMUIOO — ^MO
-It! 14
°1 20 cm 4M ^ shroud £5L >1^ (C
ASE4)
5 Inside Shroud Temperatures at 20cm (103K)2
OOOOO — — —
OhJ4^CDDOOhJ^k O) 00 O
HS-TEM
P.1100505
TIME
(103s)
ZLj
13 ^ it °1 80 cm
n ring ^*95.-8- -&
S- (C
ASE4
2R Fuel Rod Temperatures at 80cm (103K)>
o o o o M hJ M CrloojcntoMcnoo —
o o o O O —> —•
Inside Shroud Temperatures at 50cm (103K)
jj om*-oiooom*.oio»o
HS-TEM
P.1100805
Z2^ 15
40 cm
shroud -SrS. >It§- (C
ASE4)
Q O O O O ^ —• —* «• ^ fsj
Inside Shroud Temperatures at 40cm (103K)
Oro^OiCBON^OiOlO
HS-TEM
P.I100705
O O O O O —» —» —* —» —^ fsj
Inside Shroud Temperatures at 70cm (10JK)
ON)^0)OON)A(7)00O
HS
-TEM
P.1101005
TIME
(103s)
17 ^-3
°i 60 cm v*
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Inside Shroud Temperatures at 60cm (103K)7S > m 2
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P.1100905
Insi
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3K)
HS-TEMP.1101105
KAERI
19 80 cm # shroud -SrS. (CASE4)
center ring at.at
absorber cladding Guide Tube
second ring third ring
Fuel Cladding Fuel
1
Cladding
Agbln+Cd
Stainless steel
nv™ Stainless steel oxide
i------ 1 Zicaloy
ZrO,
UO !
J.% 20 % 2c ^91 (22000 £)
42
J-^22 ^%
# (Y S)) M
l ^-6- A ££. A 5 (C
ASE4)
> Vapor Temperature in Hz pipe with Y point (103K) 2
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CASE4 Vapor Temperature in Vertical pipe(l03K)7;> mO O O O O —* «« —» —* —* fsj
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?) 24 4^# (G "9) M
l >|-£ (C
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4)
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Vapor Temperature in Hz pipe with G point (103K)
o o o o o hJOM4^O)00ON)4^CnCDO
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CASE4 Vapor Temperature in SG U tube down(l03K)>m7;
o o o o o ro
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CVH-LIQLEV.700-4.20
-4.22
-4 . 24
-4.26
®-4 . 28
-4 . 30
-4 . 32
^-4.34
-4 . 36
Swollen liq level
SUMP WT LEV— 4.38
-4.40 V
KAERI
26 2| ^--8-^1 4" sump '-)) f (CASE4)
45
REL
EASE
FRAC
TIO
N
$ R
ELE
ASE R
ATE
(10" F
RAC
TIO
N)
RELEASE RATE :
CLASS4-I Gap Release
CLASS4-I No Gap Release
DATA
TIME (101 * 3s)
0.^21 Gap ZN# (Iodine )
1 0
1 0
1 0
1 0
1 0
1 0
1 0
1 0
1 0
KAERI
RELEASE Rate FRACTION :
Llti 28 Cs -c-i"
46
1 0
1 0
1 0oy—O<cc
1 0
£ 10 -< ac
< 10
£1 0
1 0
1 0
KAERI
Te129mRELEASE RATE :
CLASS 5-Te
DATA
29 Te
o 10h-oS 1 ou_
£ i occ% 10 <UJ
£ 10
1 0
1 0
1 0
KAERI
Tl'r) 30 Ru ^
47
1 o'3
O
10'5
V) 1 o'6
o> fs.1O
LtJk—<ct: 1 o'8
LUin< 1 o'9_jor O
1 o-"
1 o'12
Oi
KAERI
RELEASE RATE : Xei------- 1-------- 1--------1— —i-------- 1--------- 1-------- 1-------- 1-------- r ' !
............. CLASS1-Xer * DATA ]
r: .. •
i
r 1
r : . 1
r i-•
r 1
r i
r * •
******r
* f i
■ i____ i— 1 1____ 1—*—1--------- 1---------ii____i____ :
0 4 8 12 16 20
TIME (103s)
n.% 31 Xe'#'#
RELEASE RATE : Sn
zo
1 0
1 0
1 0
1 0
u 10c:Li_^ 10
2 10m < 1 0
“ 10
1 0
1 0
1 0
KAERI
-L'H 32 Sn (In, Ag)lM £"8-
48
ill Vl ?h2 24 212
Debris4444
t-4 4 U filial4#2l volume 4
44f4 44 -8-8-4- 2 4 21
CASE 1 °J3)
YES 1, 1 Off
CASE 2 NO 1.1 Off
CASE 3 NO 1 A ^ « Off
CASE 4(2|# 78^5 °J^)
NO 3,4 ON
3.2 MELCOR Class 1 2.^
Xe CS Ba I
He, Ne, Ar, Kr, Xe, RN, H,N
Li, Na, K, Rb, Cs, Fr,Cu
Be, Mg, Ca, Sr, Ba, Ra, Es, Fm
F, Cl, Br, I, At
Te
O, S. Se, Te. Po
Ru
Ru, Rh, Pd, Re, Os, Ir, Pt, Au. Ni
Mo
V, Cr, Fe, Co, Mn, Nb, Mo, Tc, Ta, W________
CeTi,
Zr, Hf, Ce, Th,Pa, Np, Pu, C
La U Cd Sn
Al, Sc, Y, La, Ac, Pr, Nd,Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Yb, Lb, Lu, Am, Cm, Bk, Cf
u Cd, Hg, Zn, As, Sb, Pb, Tl, Bi
Ga, Ge, In. Sn, Ag
B ILO Concrete
B. Si, P H;0* Bold : 419-44 2-4$ 4 $* Bold + Non-bold : MELCOR 44 2.444-1 4~f
49
(7) R.R : Research Report
T.R: Technical Report
A.R : State-of-the-Art Report
7) 4 4 2 4 4
749 7| #52*1 45 4444227)45 5#527)o)5 INIS 7422
KA ERI/TR-7 51/96
7)14/77)1 PHEBUS FPTO #4# 4## MELCOR 22^7}
4773)44 4 #7)4 (TR,AR4 77) 4) 4#4(#44244#4)
4 7 4 4 # 7) 4 27j4(#cfl7l-J16ll7) 5.0^ 4 Sl #(#471-315)14 W-O):)
% 4 4 IN?!# #7444472 4 vi 1996. 7
5)1 °] 4 p. 49 £ & Si #( v), Si-§-( ) H 7] 26 Cm.
#27}^ '95 #444-7)1
444- #4(V), 444( ), _#44 227) O Tf 47527)
4-444714
2# (15-20#5)19])
7)1# 4 S.
°1 227)# MELCOR1.8.3 2£f °l-g-5M PHEBUS FPTO 4#4 t-ijiAj.
444 4#444#4 44 £4 44# 7)14 44. 44444
melcor4 2c4444 ^#47M# 444 44 a## 244
44*4 4444 ?II4€ 7 44 #4# 4444 5414. 4 47444 44 2.44 #^.44ti 4444 4-5-444 '3'444 4&H 442^-4#74, 4444# 7)14444. 444 44ao)| 44 5125. 442 pellet 4
debris * ^###7} 474, 744 4444 44 5125 444 44
44-44 444 44## 42 4# 7 447} 4 #4 44 51444.
444 7)14*114 2##7# 744, SG 7)14 44 42444 7}^#57l-
#447)1 444 44# 2444 4444 74 44 5144. #4
MELCOR 44 7)1445544 Ag, In, Cd 44 #44 4## 2444
244 Si4. 4471 7)l4-g-!-4 4# 544 47}7} 45442 4444.
#4^7)42(104444)
PHEBUS FPTO, MELCOR1.8.3
BIBLIOGRAPHIC INFORMATION SHEET
Performing Org. Report No.
Sponsoring Org.Report No.
Standard Report No. INIS Subject Code
KAERI/TR-751/96
0T‘tle{ Evaluation of MELCOR Code Using PHEBUS FPTO TestSubtitle
Project Manager and Department Jong-Hwa Park(Severe Accident Analysis)
Researcher and Department
Song-Won Cho, Hee-Dong Kim(Severe Accident Analysis)
PublicationPlace Taejeon Publisher KAERI Publication
Date 1996. 7
Page p. 49 Fig. & Tab Yes( 0 ), No( ) Size 26 Cm.
Note '95 Mid-Long Term Project
Classified Open( 0 ), Restricted( ),__ Class Document Report Type Technical Report
Sponsoring Org. Contract No.
Abstract 15-20 Lines) This report presents the analysis results of the PHEBUS FPTO experiments using
MELCORI.8.3 for the core degradation process, the fission product release in the
circuits. The objectives of this study are to assess the models associated with the
core damage and fission product behavior and to identify the phenomena, which
have not been modeled, or area where the model could be improved. The
calculation results were much improved by performing the sensitivity studies for
the three phenomena, which were considered important to simulate the test senario.
The first case is to consider whether the debris formation is to be allowed or not.
er whether the oxide layer can hold up the molten mixture or not and the third case
nodalization for the U tube in the SG and the vertical pipe at core exit, where the
ed rapidly during the transient. In MELCOR, there is no model that can simulate
from the control rod but from the fuel during the fission reaction. Therefore, it is
lodel from control rod should be implemented into the MELCOR Code.
The second case is to consk
is to consider the number of
gas temperature was chang
the release of Ag, In, Cd
considered that the release ir
Subject Keywords (About 10 words) PHEBUS FPTO, MELCORI.8.3