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{{#Wiki_filter:__ - _ _ _ _ _ . | {{#Wiki_filter:__ - _ _ _ _ _. | ||
l-i | l-i HYDROGEN SOURCE TERM FOR BWR DEGRADED COPI ACCIDENTS i | ||
i 1 | |||
BY GARRY R. THOMAS NUCLEAR SAFETY ANALYSIS CENTER NUCLEAR POWER DIVISION ELECTRIC POWER RESEARCH 15STITUTE PALO ALTO, CALIFORNIA; USA i | |||
PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION | |||
PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION 3ETHESDA, | : 3ETHESDA, MARYLAND i | ||
29 Juts 1983 k | 29 Juts 1983 k | ||
8409260147 840910 PDR ADOCK 05000458 | 8409260147 840910 PDR ADOCK 05000458 G | ||
PDR | |||
D | |||
= * = = = = =.. | |||
.g. | |||
O O | O O | ||
e t | e l | ||
t I | |||
DEGRADED CORE PHENOMENA 9 | |||
a C | |||
C | |||
( | ( | ||
O | O | ||
+ | |||
4 e em h a | 4 e em h | ||
a | |||
? | |||
+5: | |||
I 4 | |||
0 t | |||
i | |||
2 | 2 | ||
~ | |||
CORE DEGRADATION WITH INSUFFICIENT COOLING | CORE DEGRADATION WITH INSUFFICIENT COOLING DEGRADED CORE ACCIDENTS GENERALLY INVOLVE DECAY HEATING | ||
..e OF CORE DUE TO SUSTAINED INADEQUATE CORE COOLING e | |||
e | CORE DEGRADATION PROGRESSION CHARACTERIZED BY: | ||
e RELATIVELY SLOW INITIAL HEATUP RATES WITH STEAM COOLING | |||
~ | |||
e LATER DOMINANCE OF ZIRCALOY OXIDATION EXOTHERMIC ENERGY RELEASE | |||
'e RATE LIMITS FROM LOCAL STEAM OR. STEAM / HYDROGEN CONDITIONS HIGHDEGREEOFNONC0HEREiiCYI0FCOREDAMAGE s | |||
e SPATIAL DISTRIBUTION e DAMAGE SEVERITY e | |||
RELATIVELY SMALL SYSTEM RESPONSES REQUIRED TO ADEQUATELY SUPPLY SUFFICIENT COOLANT SUPPLIES / HEAT SINKS FOR: | |||
'i e | |||
PREVENTING CORE DAMAGE DUE TO OVERHEATING INTERRUPTING CORE HEATUP/ DEGRADATION, PROCESS e | |||
Q 5 | |||
GRT 6/83 i | |||
) | |||
80.. | |||
gNRCCladdingOxidationCriterion=75% | gNRCCladdingOxidationCriterion=75% | ||
3 | 3 70 3 | ||
70 | Approximate Range in Cere-Wide Cladding Oxidatien j | ||
Fraction in Unmitigated Degraded Core Accident | Fraction in Unmitigated Degraded Core Accident | ||
*s J'! | |||
J | 60 - | ||
3l 2 | |||
5 8 | |||
j 50, | |||
.i g | |||
t 8 | |||
j | e 40, | ||
j | |||
-3 | |||
/ | |||
j' | |||
.i e ' | |||
3 o | 3 o | ||
j 5 | |||
I | 30 I | ||
-/~ | |||
4 | |||
i | ./, | ||
? | |||
s | / | ||
:ll i | '/ | ||
l t | |||
i | |||
.3 I l l | |||
. l ~,- | |||
.ili s | |||
u | |||
:ll y/ | |||
lf., l l' i | |||
! i i | |||
//'/ | |||
2 | |||
-.i | |||
.i ll | |||
f ,' j / | / | ||
/ | |||
/ | |||
/ | |||
/ / ll | |||
*a | |||
, / | |||
/ | |||
/ | |||
Water | 10 | ||
~/ | |||
/ | |||
/ | |||
JY | I a | ||
27 June /W3 1 | f,' j / | ||
1,_ | l | ||
/ / | |||
l I | |||
l | |||
/ | |||
0 l 2000''F-to l3500'Fto Time I | |||
5200 'F (UO h > 5200 'F 1 | |||
Core Max | |||
< 2000 'F | |||
,-3500 'F (Zry 2 | |||
Temp Melt) l Melt) l g | |||
I Water Top | |||
] | |||
Level of | |||
,~ 3/4 Un._~ 9/10 Un-4 | |||
- v Core covered covered i e O | |||
i Geccetry Essentially Intact | |||
-Local Dis--Generali::ed Sjcr Slumping /EF'l 5::::- | |||
tortion anc Slumping Head Failure slumpine Beginning t | |||
JY 27 June /W3 1 | |||
1 1,_ | |||
1 1 | 1 1 | ||
( | ( | ||
BWR CORE HEATUP CODE 9 | 1 BWR CORE HEATUP CODE 9 | ||
MODELING BASIS | MODELING BASIS | ||
.I | |||
[ | [ | ||
l 1 | l 1 | ||
i | i I | ||
1 i | |||
i | -i l | ||
.l. -. | |||
'h | |||
'ij t | |||
s | |||
.i. _ | |||
O l | O l | ||
1 o | 1 o | ||
....a | |||
t i | t i | ||
4 1 | 4 1 | ||
STEAM DOME | STEAM DOME | ||
/ | |||
/ | |||
i | |||
~ | |||
/ | |||
I,/ | I,/ | ||
/ | |||
( STEAM 1 | |||
I i | |||
l 4 | |||
......L..... | |||
~ | |||
!',,,,,ydPERPLkNUM N | |||
j | |||
[M "3 | |||
i.* l | 0 0 | ||
4 8 | t | ||
~i r | |||
- e ECCS-1 c==r | |||
...,,' -l l | |||
W l | |||
d | I i.* l | ||
m), | ( - | ||
i 4 | |||
8 l | |||
{ | . 65d'll FEECWATEF l' | ||
=: | |||
i lf | |||
$: d m), | |||
u | p | ||
= | |||
r k 55 a, | |||
{a | = | ||
{ | |||
a | "T"t.' | ||
s | t. | ||
o. | |||
s. | |||
~ | |||
i 4 | 0 d | ||
4' w s s | |||
4 I | u | ||
~- | |||
i, | s o | ||
{a i w j | |||
r, a.. | |||
s - | |||
, s. | |||
s v | |||
./ | |||
i MODEL BOUNCARY w | |||
n 1 | |||
s y," | |||
A y< | |||
g a | |||
E E | |||
a o | |||
s m | |||
a. | |||
E LCWER PLENUM E | |||
i 4 | |||
k I | |||
i | |||
.1 i | |||
CRD 1 | |||
4 I | |||
BWR CORE HEATUP MODEL 4 | |||
i i, | |||
1 | |||
-m. | |||
i | i | ||
( | |||
t, | t, j. | ||
BYPASS | ^ | ||
BYPASS CMNNEL CHANNEL i | |||
m. | |||
y t | |||
I SHROUD CHANNEL l~ | |||
~ | |||
FUEL CHANNEL s'-' | |||
f WALL CONTROL WALL W | |||
f | / | ||
ROD (gCLAD f | |||
i | |||
( | ( | ||
8 J | 8 J | ||
l s | |||
i 1 | i 1 | ||
j s | j s | ||
L- | L-TUEL pygt RCD ROD TYPICAL. | ||
AXIAL | j[ | ||
l | AXIAL I | ||
STEM i | NODE b@ | ||
f | +Q e i | ||
l | l STEM i | ||
f l | |||
l b O., | |||
,0* | |||
'l ty. | |||
~~s' y | |||
I j | |||
,/ | |||
O 2 | |||
] | |||
') | |||
~ | |||
w y g | |||
i' | '4ATER y-e a | ||
i | |||
~ | |||
i' i | |||
LOWER PLENUM BWR CORE HEATUP CODE CORE MODELING I | |||
1 1 | |||
l 1 | l 1 | ||
i | i i | ||
1 | |||
Corner Rods | Corner Rods Side Reds | ||
- (4/Bundl e) | |||
(24/ Bundle) | |||
\\ ___ 6'@ O.O @__O_ | |||
D l | |||
O FO O O O O OIO | [OlOOOO@010' c,,,,,3 OOOOOO!O O FO O O O O OIO (34/sunete) | ||
(34/sunete) | OOOOOOOO OOOOOOM I | ||
O O O O rgit o o!o oo o o o;Oo OO[efdOOIO OOO O Oi I'l';&,1 | |||
.010_O_O_O O OlO | |||
~ | |||
0 0'@ | 0 0'@ | ||
@iO O O O O Ol@ | |||
@00 OO!O_ | |||
Slade | Q O @ O O @ OlO,j_(*010 0 0 0 0 07 0,> | ||
Centrol e | |||
Slade 1( | |||
OIOOO140OO | l l | ||
) | |||
*OlO @ OO @ 010" | |||
'OlO @ O O OOICf OlO O O O O OlO OlO O O O O OlO l | |||
O O O O O O Ol@ | |||
I._ | OlOOOO0010 doO[elOOOO OlooOr,]ool0 OIOOO140OO OIO O[eTOOOO | ||
~ | |||
01000000@ | |||
O!O OOO OO O i | |||
010000000 01000000 | |||
: pOeOOeOO, pO eOO eOl0_O, FOUR 8UNDLE FUEL WCOULE O ~''a" o -m x, h Tit RCCS BWR CORE HEATUP CODE UNIT CELL CONTAINING 4 FUEL BUNDLES AND 1 CONTROL R0D BLADE | |||
.i I._. | |||
o | o e | ||
TOPviEW e | |||
a" | DODODODODO a '' | ||
00TQ000000000 i | |||
a" 00000000D0000000D0 i | |||
DODCDODODODODODORODODO | OOODODODODODOOnnGDOD | ||
~ | |||
44,, | |||
DODuuCDuuGDODODLluGDuuO a., | |||
DODCDODODODODODORODODO 0000D0D00E0000D0D0D000 | |||
.=,, | |||
QOOOODODQDCDQDODQDODonOO | |||
= | |||
"- DODODuuGDODODODODuuCOGDODO | |||
= " DODODOPODQDCOODODODODODODO | |||
= " | |||
D000D000D00000D0D000000000 | |||
= | |||
u" D00000000 | QDOD nrTQRnnO Dnn GD Q | ||
''~ OGOOOTOD OCT i | |||
= "- | |||
DODODuoODOD iODODODODODODOI | |||
D00000D | = | ||
D0000000D | |||
'Q]GDODODODODODOl*. | |||
=u" D00000000 uO3LTOODODDDUOuL.NU n" ~ DnnODQOOOCDOCI9J]CD00000D0D0 L | |||
vol' DO^OODuufDEDODODODODODuoODO | |||
l D0D0D00000 iIIIIIIIi1 | 'a,, _R00000D00000D0000000000000 0000000D0D00000000000000 i. | ||
S | i OOOJODOQGDODO CTOOOROD ri i | ||
TCTAL PENE* RATIONS FCR NUC1. EAR IM$TRUutNTS 43 BWR/6 CORE MAP SHOWING RADIAL ARRANGEMENT OF BilR | T i4 D00000D L000D00C000U00 so " | ||
T | |||
!OODQDODODODODOD 0D000 | |||
=, | |||
10D0000000D000D t_.ODOC | |||
=,, | |||
OODODODODODODODODO o. | |||
I I I ODODODuuCDuu n,l1li1 l 1 l D0D0D00000 l | |||
iIIIIIIIi1 83333 2 :: | |||
A R R A R 9 : ; ; ;R a a s a s.: : : :: a===naanaa: : : : : - | |||
S CE ANGE MCN TCa u | |||
3 w EawEo: ATE aAuct uCNiToame sysTEu naus a | |||
TCTAL PENE* RATIONS FCR NUC1. EAR IM$TRUutNTS 43 BWR/6 CORE MAP SHOWING RADIAL ARRANGEMENT OF BilR CORE HEATU? CODE UNIT CELLS i | |||
I | I | ||
l l- | l l-764 Bundle Core Half Core Map - Typical for 2nd Fuel Cycle | ||
764 Bundle Core Half Core Map - Typical for 2nd Fuel Cycle | ( | ||
(numbers in bundles re: resent different enrichment or exposure) so 2Ts 121: 14 lii n la 14 Trl s i sjTT a 3 | (numbers in bundles re: resent different enrichment or exposure) so 2Ts 121: 14 lii n la 14 Trl s i sjTT a 3 | ||
' 2 T T s i sj I I s Il21. s ig s i 2 ' | |||
Yis lIIIIIII[II'sTsT2[ sis j sIj, ITj s l41212 l2.sgsIDsi sis 2l2] | |||
212[sia slal4lal41:14l:y41 14 3141: 14 214 sl41 sis sist:12 | 2I tit ss 212[sia slal4lal41:14l:y41 14 | ||
,4 3141: 14 214 sl41 sis sist:12 j | |||
1 | ns | ||
sim b 41s | -[s spi s s l 2 f_I[TQ ds-[U si2 slDT2pT2pi s' 21s1 2 2 | ||
1 sim b 41s 4 l 2. 4 Isi s l s ls ta ls 212 22 2121s 21s alsis 4 1 s, 4 l :, i 4 : s 21sI23}U21:12 s i s i s i s 9: 12 s i s l a lhiIs l 21 s llT sT | |||
ts :l 2 l s 121.T Ti s1g1sp i s lsk): | '28 212!2121sl2 ts :l 2 l s 121.T Ti s1g1sp i s lsk): | ||
sl l4 s;s!sisjajsj2l2 I | |||
s | T4 4143 314 4 | ||
l 2 l | 3 'y sa l s l 2 l.s l 2121 s l 2 : 2j 1s t 2 l 2 | ||
12 l s 2!s sls s!sisl4 4 s i s 's sI 2 .s'2 sl21sl | : ja 2g2 2l sis 8 s l s t s l s : s,l l 2 g l 2 l 2 2 | ||
s 14 - | |||
_2,}127sJ212 | s.21s sis Is isie ls ls l: 13 41s gt2l: | ||
od - | 4 a s | ||
2 DI2Ts'l 2Tsi2l 2'sisis TfTl2': 's 2's12;shl~2T2I2' | |||
( | |||
12 - | |||
21s sl4lsl4 | 12 l s 2!s sls s!sisl4 4 s i s 's sI to - | ||
2.s'2 sl21sl | |||
_2,}127sJ212 j 212 f il s l 2 sl2:2lN2(2 sl2l2 Os - | |||
slystag22s 2 212 21si21sjJs sls12 os -- | |||
TYPICAL 764 FUEL BUNDLE, 231-INCH RPV SWR /6 CORE MAP SHOWING RADIAL ARRG'T OF BWR CORE HEATUP . CODE UNIT CELLS l | 2 g | ||
als]ll od - | |||
421sgrisj21s gsisisl2lsl2 sl2 2 sl 212121212 ( 21 : 12 l21212 i | |||
u ii 01 Os 05 07 09 11 12 1s 17 is 21 222s27 3 s1 ss X 27 3 41 43 46 47 el si ss ss s7 sg Quarter Core Map showing Unit Cells and Their Core-Wide Grouping Unit Cell 1 sl8 l'' s18 sl' sls 214 | |||
: 12 sl2 s ls 214 sla s14 sis 214 sl2 sl2 Unit Cell 2 213 sis s_Q sis sit sls 2 | |||
s2 414 sl4 14 sie 214 2ls ls 2.2 Unit Cell 3 sis at | |||
:21s l: | |||
si s 212 s12 si: | |||
21s sl4lsl4 314 als als als 212 Unit Cell 4 sls alsj212l21s 213 2Is 212 sl2 a l4 314: 314is14 sls als 2is 2{2 | |||
,,2] | |||
21sja :sls Unit Cell 5 3 | |||
2 s : 212 2 | |||
2 2 | |||
5 2 | |||
s Is S | |||
Is 2is b | |||
2 2 | |||
l4e s Unit Cell 6 | |||
*l' ''8l21s121sl2l sis l2 212 2is!21sl2l: | |||
4l4 s | |||
sis s | |||
Unit Cell 7 212 s l 2 : 2 l 212 l 2 8 s i s ; s, 212 2 l s ir i s l21 s l st a 8 2 sl s st2lsl2 s i 21 Unit Cell 8 2' | |||
21:1212 2 | |||
l: | |||
TYPICAL 764 FUEL BUNDLE, 231-INCH RPV SWR /6 CORE MAP SHOWING RADIAL ARRG'T OF BWR CORE HEATUP. CODE UNIT CELLS l | |||
Radial Power Shape-- | Radial Power Shape-- | ||
Function of Position | Function of Position Core Axial Power Shape-- | ||
Core | For All Unit Cells i | ||
CL Unit Cell (4 bundles) | |||
Cell (4 bundles) | |||
I I | I I | ||
I l | I l | ||
I | s I | ||
l | l I | ||
i I | |||
Onq | l 3 | ||
Nde | I' 1 | ||
i Onq i | |||
I Nde o | |||
I I | |||
Axial | |||
Radial Direction i | ^ | ||
l Direc-I tion l | |||
AXIAL AND RADIAL PEAKING FACTORS i- | 1.0 l | ||
P/ P,y, i | |||
13 P/P Distance Frem Centerline n | |||
Radial Direction i | |||
? | |||
AXIAL AND RADIAL PEAKING FACTORS 4 | |||
i-w n | |||
' ' - - - ' ' ~ | |||
i | i Unit Cell 4 Unit Cell 3 Unit Cell 2 Unit Cell I p __ qimarje____) | ||
Unit Cell 4 | p _ _Im,agep __ _ q.. _ _ _ _ Image.r - 7 P--i r - -- 1 Image I | ||
I '1 ! | |||
I! | |||
_ _( l ll | (l! | ||
i l | |||
L . _ _J | l l'Il l | ||
L._ _.I [ L -- _.J._._ _ J (l! L _ __1 L | |||
_.ll l L _._ _I H | |||
A A | |||
H A | |||
11 A' | |||
H L.__.lj'L__J cJ i | |||
c =,t a | |||
_ _ = | |||
r r.= | |||
c 881 - - l F - | |||
ll'r-1 | |||
- - -M l - ~ 1 l_-_-gr__0q l | |||
F- -~ ~l lI l J | |||
g l | |||
A.J C | |||
I l | |||
ld' C | |||
I | |||
_ _( | |||
l ll c_J I | |||
A IlI l | |||
A i | |||
I C | |||
i L. _ _J L __ J L _ _J | |||
_ _ _l | |||
_ ? _l L ^_J L _.J L _ _1 l | |||
1 | |||
( | ( | ||
Unit Cell 4 | Unit Cell 4 Unit Cell 3 | ||
. linitCc1T2 Unit Cell 1 o | |||
I H | |||
A H | |||
increasing __ | A4 2 2 11 A 4 | ||
J | ~ | ||
2h! - Il A | |||
CMI 20 | increasing __ | ||
J 2 | |||
m p | |||
mirror image transtt.of L[T'~l | t core radius h | ||
A C | |||
A C( i; A-CMI 20 A C | |||
a | |||
/s As l | |||
I mirror image transtt.of L[T'~l | |||
, 21.' | |||
d2lmuthal radiant energy | d2lmuthal radiant energy | ||
+H l | |||
l A | |||
l ll - hot hundle i | |||
A - average bundle | |||
L _ _J | ' [_ _ _. b _ __ j C - cold bundle r _.x x> | ||
i r-lfr- -I 1 | |||
A I)I C | |||
l i | |||
L _ _J L __ J Unit Cell 2 Image SCllD1ATIC 0F BWR CORE IIEATilP CODE llNIT CELL ARRANSEf1ENT TO ACC0llNT F0it RADIATION BETWEEN ADJOINING BUNDLES AND UNil CELLS I | |||
i, | i, 3: | ||
3: | 3:li-i | ||
3: | .I BWR CORE HEATUP MODEL | ||
li- | ~ | ||
i | ;i. | ||
o GROSS CORE MODEL e UP TO EIGHT FOUR-BUNDLE UNIT CELLS e CORE BOTTOM INLET FLOW HYDRAULICALLY SPLIT BETWEEN FUEL BUNDLES AND BYPASS | |||
{ | { | ||
e | e TOTAL LIQUID INVENTORY MASS & ENERGY BOOKKEEPING e BUNDLE LEVEL CALCULATIONS BASED ON MAN 0 METRIC l' | ||
BALANCE WITHIN CHANNELS - ONE BYPASS LEVEL e MASS & ENERGY BOOKKEEPING Oii VAPOR 8 HYDROGEN IN DRIED OUT PORTION OF.EACH FOUR-BUNDLE UNIT CELL FUEL RODS AND CHANNEL WILLS HEATUP FROM NUCLEAR e | |||
e MASS & ENERGY BOOKKEEPING Oii VAPOR 8 HYDROGEN IN DRIED OUT PORTION OF.EACH FOUR-BUNDLE UNIT CELL | I ENERGY AND OXIDATION (STEAi AND HYDROGEN LIMITED) | ||
I e | |||
ENERGY AND OXIDATION (STEAi AND HYDROGEN LIMITED) | CONTROL BLADE HEATUP INVOLVES THERMAL RADIATION BETWEEN BUNDLES AND CONTROL BLADES 1 | ||
I e | j e | ||
j | TOP CORE SPRAY INTO UPPER PLENUM j | ||
CCFL FLOW INTO FUEL BUNDLES | j CCFL FLOW INTO FUEL BUNDLES l | ||
'l BYPASS FILLING WITH ORIFICED FUEL BUNDLE | |||
{ | { | ||
BOTTOM INFLOW i | BOTTOM INFLOW i | ||
4' | 4' | ||
- GRT 6/83 i | |||
.l 4 | |||
l | |||
- ~. -...... | |||
o | |||
( | |||
BWa CORE HEATUP CODE | BWa CORE HEATUP CODE | ||
~ | |||
CODEFEAT0RES i | CODEFEAT0RES i | ||
G | G | ||
.--h e | |||
e 6 | e 6 | ||
e 9 | e 9 | ||
| Line 394: | Line 530: | ||
e 1 | e 1 | ||
s t | s t | ||
'i 1 | |||
e | e | ||
0 | |||
~ | |||
BWR CORE HEATUP MODEL (CONT'D) | BWR CORE HEATUP MODEL (CONT'D) e STRUCTURES OUTSIDE CORE e SIMPLIFIED AB0VE CORE STRUCTURE (STEAM SEDARATOR/ | ||
e STRUCTURES OUTSIDE CORE e SIMPLIFIED AB0VE CORE STRUCTURE (STEAM SEDARATOR/ | DRYER) - HEATED BY VAPOR & HYDROGEN FROM CORE THERMALRADIATIONMODELIEGOFSHROUDANDRPV e | ||
DRYER) - HEATED BY VAPOR & HYDROGEN FROM CORE e | WALL e DOWNCOMER LEVEL CALCULATION BASED Ofi RPV MAti0 METRIC BALANCE AND CONSISTENT WITH TOTAL RPV INVENTORY GRT 6/83 4 | ||
1 | 1 i | ||
i | i 1 | ||
i | |||
F | F | ||
( | ( | ||
.i - | |||
HYDROGEN SOURCE TERM CALCULATIONS i | |||
CALCULATIONS i | e SCOPING STUDY OF H PRODUCTION RATES COMPLETED 2 | ||
e SCOPING STUDY OF H | 6 e HYDROGEN PRODUCTION DURING HEATUP LIMITED BY STEAM SUPPLY / PRESENCE OF HYDROGEN | ||
e HYDROGEN PRODUCTION DURING HEATUP LIMITED BY STEAM SUPPLY / PRESENCE OF HYDROGEN | |||
( | ( | ||
l e | l e | ||
PROGRESSING DEGRADED CORE ACCIDENT (N0 ATTEMPT AT I | |||
s PROBABLE MAXIMUM H2 RATE PRODUCT.IO10CCURS IN EARLY PHASE OF RECOVERING-OF CORE (ECCS INJECTION) STARTING FROM ALREADY ADVANCED HEATUP (PORTIONS OF CORE AT OR ABOUT ZIRCALOY MELT CONDITIONS) | CORE RECOVERING)DOES NOT RESULT IN MAXIMUM H2 RATE PRODUCTION s-- | ||
SOMEh"dAT MUTED WHEN H | s PROBABLE MAXIMUM H2 RATE PRODUCT.IO10CCURS IN EARLY PHASE OF RECOVERING-OF CORE (ECCS INJECTION) STARTING FROM ALREADY ADVANCED HEATUP (PORTIONS OF CORE AT OR ABOUT ZIRCALOY MELT CONDITIONS) j e ABSOLUTE H2 PRODUCTION RATE PEAKS IN CORE WILL BE | ||
} | |||
SOMEh"dAT MUTED WHEN H FLOWS REACH DRYWELL/WETWELL 2 | |||
( | ( | ||
i | i l | ||
GRT 6/83 3 | |||
-) | |||
i i | i i | ||
f | f | ||
.l | |||
.c.. | |||
IlVDIV)6EN SOURCE 1ERM CALCULAll0NS | IlVDIV)6EN SOURCE 1ERM CALCULAll0NS T | ||
SCOPING SIUDY KSULTS ESULTS ACCIDENT CONDlil0NS PRODUCTION ('8"/ ge) | |||
ACCIDENT CONDlil0NS | RADIAT10N START OF CORE START OF CORE CORE FLOW 162 RtM PRESSUE (Ain) | ||
START OF CORE | MODEL UNC0VCRING (SEC) | ||
UNC0VCRING (SEC) | KCOVCRY (SEC) | ||
(LDn/SEC) | |||
1 | PEAK SUSI.41T a f M. | ||
l 3 | |||
I t | |||
3 | 0 | ||
'0.5 1.5 ($10 nin.) | |||
1 | |||
6 | '2 IULL 7200 l | ||
PRAY | 2 | ||
'2 UNIT CELL 7200 0 | |||
'O.5 j | |||
0 | |||
'0.66 1.5 ('15 nin.) | |||
3 | |||
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CUMMULATIVE MTCACGEN GENERATICM I | I l | ||
1 | i l | ||
l | |||
l | |||
t | t e. | ||
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J e | J e | ||
e h | e h | ||
| Line 1,076: | Line 1,349: | ||
ene m | ene m | ||
0 a | 0 a | ||
e 9Slp h 9 | e 9Slp h | ||
9 i | |||
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l | |||
i ig. | i ig. | ||
I | I TIME VERSUS MAX. CLAD TEMPERATURE r | ||
TIME VERSUS MAX. CLAD TEMPERATURE TEST 5B: SATURATED CORE SPRAY | TEST 5B: SATURATED CORE SPRAY | ||
g | .g g | ||
g g | |||
2000 | i 2000 i. | ||
1500 ng e | |||
1500 | ~ | ||
1000 500 l | |||
~l I | |||
l o7000 8000 G000 10000 TIME AFTER SCRAM (SF.CONDS) l 4 | |||
J n | |||
500 | y | ||
l | _. _.-g- | ||
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J | .y y | ||
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s i | |||
4 | 4 | ||
==SUMMARY== | ==SUMMARY== | ||
e DETAILED BWR CORE HEATUP CODE DEVELOPED PRODUCTION RATES COMPLETED e SCOPING STUDY OF H2 e . PEAK CORE PRODUCTION RATES (g 1.5 tsM/SEC) | e DETAILED BWR CORE HEATUP CODE DEVELOPED PRODUCTION RATES COMPLETED e SCOPING STUDY OF H2 e. PEAK CORE PRODUCTION RATES (g 1.5 tsM/SEC) | ||
OCCUR FOR SHORT PERIODS (4-1 MIN) AT INITIATION OF ECCS OPEPATION e | OCCUR FOR SHORT PERIODS (4-1 MIN) AT INITIATION OF ECCS OPEPATION e | ||
FOR ALL CASES RANGE OVER 0.5-0.8 tsM/sec | SUSTAINED CORE PRODUCTION. RATES. (( 10 MINUTES) | ||
t | FOR ALL CASES RANGE OVER 0.5-0.8 tsM/sec THESERATESAREATCORE-ACIUALPEAKRATESTO e | ||
TO DRYWELL/WETWELL WILL BE LOWER (MUTED) AS A RESULT OF PRIMARY SYSTEM THERMAL HYDPAULICS t | |||
GRT 6/83 g | |||
"a | |||
-,v | |||
1 t | 1 t | ||
TIME VERSUS TOTAL MASS OF HYDROGEN AND SENERATION RATE | TIME VERSUS TOTAL MASS OF HYDROGEN AND SENERATION RATE TEST 58: SATURATED CORE SPRAY 500 | ||
TEST 58: SATURATED CORE SPRAY | .I I | ||
500 | . _I i | ||
: - TOTAL MASS 400-x RATE | |||
~ | |||
: - TOTAL MASS | 0.S 0 w | ||
400-x RATE | 0.80 o M | ||
300 m | |||
0.80 o m | w tn v3 s | ||
w v3 | e I | ||
x 0.40 ~w i | |||
200 p | |||
H a | |||
o r | |||
a | s C | ||
D.20 100 | |||
D.20 | = | ||
,2 | |||
'I I | |||
I O | |||
O | 7000 8000 0000 10000 TIME AFTER SCRAM (SECONDS) | ||
I 4 | |||
TIME AFTER SCRAM (SECONDS) | .a I | ||
I | |||
4 | |||
1 | 1 | ||
~ | |||
i l | |||
l f | l f | ||
. _, _. _ -....., _.., _ _. ~.,. - - - -.}} | |||
Latest revision as of 07:12, 13 December 2024
| ML20098B538 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 06/29/1983 |
| From: | George Thomas ELECTRIC POWER RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20093C471 | List: |
| References | |
| NUDOCS 8409260147 | |
| Download: ML20098B538 (42) | |
Text
__ - _ _ _ _ _.
l-i HYDROGEN SOURCE TERM FOR BWR DEGRADED COPI ACCIDENTS i
i 1
BY GARRY R. THOMAS NUCLEAR SAFETY ANALYSIS CENTER NUCLEAR POWER DIVISION ELECTRIC POWER RESEARCH 15STITUTE PALO ALTO, CALIFORNIA; USA i
PRESENTATION TO U.S. NUCLEAR REGULATORY COMMISSION
- 3ETHESDA, MARYLAND i
29 Juts 1983 k
8409260147 840910 PDR ADOCK 05000458 G
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CORE DEGRADATION PROGRESSION CHARACTERIZED BY:
e RELATIVELY SLOW INITIAL HEATUP RATES WITH STEAM COOLING
~
e LATER DOMINANCE OF ZIRCALOY OXIDATION EXOTHERMIC ENERGY RELEASE
'e RATE LIMITS FROM LOCAL STEAM OR. STEAM / HYDROGEN CONDITIONS HIGHDEGREEOFNONC0HEREiiCYI0FCOREDAMAGE s
e SPATIAL DISTRIBUTION e DAMAGE SEVERITY e
RELATIVELY SMALL SYSTEM RESPONSES REQUIRED TO ADEQUATELY SUPPLY SUFFICIENT COOLANT SUPPLIES / HEAT SINKS FOR:
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PREVENTING CORE DAMAGE DUE TO OVERHEATING INTERRUPTING CORE HEATUP/ DEGRADATION, PROCESS e
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