KAERI/TR-751/96 KR9600282

PHEBUS FPTO U^^ O|goh MELCOR 3 EEvaluation of MELCOR Code Using PHEBUS FPTO Test

1996^ 9 1

Korea Atomic Energy Research Institute

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Phebus FPTO U&% O\g^ MELCOR 3 E ?p|-Evaluation of MELCOR Code Using Phebus FPTO Test

1996"d 91

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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.

The dissolved mass of UO2 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 burnup 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.

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29

fife S^olfe uo2 g

zr a&si iJ3£# ems] uo2

2,500 K O|| £#SO|| O|D| # S ^ t O | #£S| S^EjCH g § £ £ ^ Zr

HSoll uo2 §sHgo| 5J7|| oj|^£|2icK ^ ^ Eutectic

SSE7I- MELCOR 3HO(|A1 5 ( g * m Stlfe lumped

r & ^ *F°l7r 9X%E[. ns|L|. o | ^ ^ ^x- | | l «||g control volume

activation product

MELCOR 2HU

h ^ S I H ^ 8 3HLH0|| S7|0|| ^XH^fe UO2

^ uo2 S ^

o|

ring S 17H°| ring °

^ £ S2JS0I on-|2 2|¥ driving core

O| ^ ^ o | g^£f ^O| «l|oiSS0| &X\ 9<U?}

§ 2 | g g ¥A|*h5SCK EE& AhgS ^ £ g O | ^2] fresh

gap ^ s f i f i o.o 2 ? ^

30

71 oil £

CORSOR

- S S ejsH Class2 (Cs), Calss3 (Ba), Class4 (I), Class5

(Te), Class6 (Ru), Class7 (Mo, Co), Class8 (Ce, Zr), Class12 (In, Ag, Sn) 5_k)|

Cadarache

| H , K R u 9 ^ ^

1 5 , 0 0 0 o | ^ t n f c H S ^ I ! J £ ! K j ^ 9 l | ^ t # f H

MELCOR ^ H ^

31

1. I.Shepherd, LHerranz etc, "Pre-Test calculation for the Thermal-hydraulic Tests

carried out in the PHEBUS-FP Containment Vessel" JRC, 1994.

2. A. Arnaud, 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 SCDAP", 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

n

CO

•Si

CO

3Q.

rdOS

i"

BI ^

protective layer —

inner layer fj

steamgap u

outer Uyer *•

steam gap

sleeve »

pressure tube M

B" 3 ^

-<

I.s

•SE

cen

orah

w

Outside Shroud Temperotures ot 60cm (1O3K)

o —• —

sir

oo3

c

4*

o

oo -

oM

>CO

m

>GO

m

o>

too

—. — - » NJ

*>. cn CD o

1 11

-

-

f I

1

v\

-

-

• •

1 J

11

\

c1 1

1 1 1

•

•

f \

j(b

11•ur:

TC7

* "

1

|

i

- CASE

~*

I

•• CASE

-

-

-

-

-

-

M

r>

n>

Cumulative H2 Production (iO~!Kg)

o oo —

o oen

o o

00

o

10

00

°?n00n

—1•|MIo ~

u ls>

o> •

K>O

o 0 . 4o

0 . 2

0 . 0

KAERI

CASEJ

CASE2

-6.6«2m :TC49-6.402m :TCS0-6.»2m :TC51-5.982m :TC52

8 12 16

TIME (103s)

20

J-^ 5 (CASE2 / CASE3)

O

o

alda

dow

ntu

be

om_c

Tem

pera

tur

Vap

or

2 . 0

1 . 8

1 . 6

1 .4

1 . 2

1 . 0

0 . 8

0 . 6

0 . 4

0 . 2

0 . 0

KAERI

V

I I I I l_

CASE3

CASE2 3.010-4.515m

TEPF722: 2.955 m

_l I I

- 1¥J 6

4 8 12 16 20

TIME (103S)

I " T T M ?sTi- >"-|-k(CASE2/CASE3)

35

The second ring cladding temperature at 60.0cm ( X 1 0+ Cumulative H2 Production (10" 'Kg)

>m33

Inlet temperature (1O3K)

o

o

o

a-©

-u4*

fjO l / l "

n>00

m

o o0 0 CD 00

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i1

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1 1 i :5" OJ fo g r-

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i-

j

i

-

l i

>nTO

Central CR absorber Temperatures at 70cm (1O3K)

o o O o O N> hJ N> hO

3R Fuel Rod Temperatures ai 60cm (1O3K)

COGO

sirC\

oo

_o,V_vr=J,rin

g '

• * »

CD

riME

i

M

>

mo

2R Fuel Rod Temperatures at 60cm (1O3K)

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I-J

Miro

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.a ^

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tn

o

Inside Shroud Temperatures at 20cm (103K)

CO

2R Fuel Rod Temperatures at 80cm (103K)

HS-TEMP.I100705

-aO

<0

12 16 20

Hfr shroud £ £ *!•§• (CASE4)

uoin

mpe

;

o-Ct/i

2 . 0

1 . 8

1 . 6

1 . 4

1 . 2

1 . 0

0 . 8

0 . 6

0 . 4

0 . 2

0 . 0

HS-TEMP.1100805

0.S m: Col

Utasur: TC37

Mcasur: TC38

12 16 20

1I 16 50 cm shroud iS- (CASE4)

40

Inside Shroud Temperatures at 70cm (10JK) Inside Shroud Temperatures at 60cm (10 3K)

U

00

o

oa.no

n>tom

o

o

o — -*• • •oo o NJ

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a.

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KAERI8 12

TIME (V)3s)

16

H ^ 19 80 cm 9J shroud •£ (CASE4)

center ringat.at

absorber cladding Guide Tube

t

second ring

Fuel Cladding

third ring

Fuel Cladding

Ag+ln+Cd

Stainless steel

Stainless steel oxide

Zicaloy

ZrO,

£ (22000 2b)

42

52

Vapor Temperature in Hz pipe with Y point (1OJK) > CASE4 Vapor Temperature in Vertical pipe(iQ3K)

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8 8 £ s » - &

Vapor Temperature in Hz pipe with G point (103K) CASE4 Vapor Temperature in SG U tube down(103K)

U

to

om

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RELEASE FRACTION

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10

10

RELEASE RATE :

- 9

- 1 0

10

KAERI

- i i

10

Te129m

14 18

TIME (10 3 S)

Te

22

- 3

10

10- 5

. - 6

o10

- 7

. - 8

& ' 0<LJJ

£ 10

10 '

10

10

KAERI

- 9

- 1 0

- t 2

- t 3

RELEASE RATE :! 1 1

r

r

-

*

r

r

-

-

Ru

C D / Q

D • yv

/

K JN

j

-,.—-~n

cm -Q

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OS

1

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1

CLASS6-Ru V

a DATA 1;

u i J

10 14

TIME (10 3s)

18 22

30

47

RELEASE RATE (FRACTION) RELEASE RATE (Kg/s)

o o o o o o o

00

u

9$.

r-;c

CDp o a o

>• >• on

(/> > g- F3(£3 1

• D

• attB

u

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o

en

SJO

- i ' ' " — i • •

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-1 • . • • • - ! •< • • • - ' • • - - ' - • • •

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51-Xo

|

-

-

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-

m5>—H

xa

CASE 1

CASE 2

CASE 3

CASE 4

Debris

YES

NO - -

NO

NO

3-2] volume ^r1, 1

1 1

3,4

Off

Off

Off

£ 2 MELCOR °1Hs] Class .SJ ?••&

Noble gas |class 11Xe

He, Ne, Ar, Kr, Xe, RN, H,N

Chalcogcns [Class 5J

Te

O, S. Se, Te. Po

Trivalents|Class«)|

Boron ICIass 111B

B. Si, P

'Alkali mclal jClass 2| Alkaline earth [Class 3 | Halogens ICIass 4 |CS

Li, Na, K, Rb, Cs, Fr,Cu

Ba

Be, Mg, Ca, Sr, Ba, Ra,Es, Fm

I

F, Cl, Br, I, At

'Platinoids [Class 6|

Ru

Rua

RhAu.

, Pd, Re, Os, Ir,Ni

Early transition elementICIass 7|

Mo

V, Cr, Fe, Co, Mn, Nb,Mo, Tc, Ta, W

Tetra\alcn(sICIass S|

Ce

Zr, Hf, Ce, Th,Pa, Np, Pu, C

La

AlPmFrBk,

Sc, Y, La. Ac. Pr. NdSm, Eu

Tm. Yb,Cf

Gd, TbLb, Lu,

Dy,Am,

• H i

Ho,Cm

Ajraniuin [Class lOj

U

U

Water [Class I4|

H20

H:0

Ti,

More volatile main Less volatile maingroup IC'lass 111 group ICIass 12|Cd

Cd,Tl,

^ ^

Hg,Bi

Zn, As,

• • •

Sb, Pb,

Sn

Ga, Ge, In. Sn. Ag

Concrete ICIass I5 |Concrete

• Bold + Non-bold : MELCOR

49

R.R : Research Report

T.R: Technical Report

A.R : State-of-the-Art Report

s. «£ q

KAERI/TR-751/96

4 PHEBUS FPTO 4111-I- °1 -§-?!- MELCOR

(TR,AR°J 3 -f

1996. 7

p. 49 26 Cm.

v ),

fe MELCOR1.8.3 2 PHEBUS FPTO

MELCORM1

5i pellet

debris Sj-

SG

MELCOR oflfe Ag, In, Cd

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

Title/Subtitle

Evaluation of MELCOR Code Using PHEBUS FPTO Test

Project Managerand Department

Jong-Hwa Park(Severe Accident Analysis)

Researcher andDepartment

Song-Won Cho, Hee-Dong Kim(Severe Accident Analysis)

PublicationPlace

Taejeon Publisher KAERI PublicationDate

1996.7

Page p. 49 Fig. & Tab Yes( O ), No( Size 26 Cm.

Note '95 Mid-Long Term Project

Classified Open(O ), 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

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 senario.

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 tube in the SG and the vertical pipe at core exit, where the

gas temperature was changed rapidly during the transient. 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 control rod should be implemented into the MELCOR Code.

Subject Keywords(About 10 words)

PHEBUS FPTO, MELCORI.8.3