ML20059B717: Difference between revisions
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| number = ML20059B717 | | number = ML20059B717 | ||
| issue date = 07/16/1978 | | issue date = 07/16/1978 | ||
| title = Radioactive Decay Heat Power Data | | title = Radioactive Decay Heat Power Data | ||
| author name = | | author name = | ||
| author affiliation = GENERAL ELECTRIC CO. | | author affiliation = GENERAL ELECTRIC CO. | ||
Latest revision as of 21:35, 6 January 2021
| ML20059B717 | |
| Person / Time | |
|---|---|
| Site: | 05200004 |
| Issue date: | 07/16/1978 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20059B690 | List: |
| References | |
| 22A5792, 22A5792-R01, 22A5792-R1, NUDOCS 9310290069 | |
| Download: ML20059B717 (11) | |
Text
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! l 1 i GEN ER Al.h ELECTRIC 22A5792 so o. 2 {~
NUCLEAR ENERGY DIVis!ON i i
- 1. SCOPE 1.1 This document specifies the values for the decay heat p er frts fission products and the heavy elements U-239 and Np-239, following the shutdown of General Electric Boiling Water Reactors (BWR/2-6) containing U-235. U-233 cnd
( Pu. The decay heat pwer values for the fission products and heavy elements are presented in analytical and tabular form. 1.2 The decay heat power values in this document shall be applied after July 1, 1978 to all future analyses (including revisions) deoendent on decay heat but shall , not be backfitted . Based on BWR licensing corrattments, plant ecuicsent limita-tions and tne ongoing revision to the Proposed ANS Standa.d (Oct /3 revision) the oecay heat power values are specified for applications as follows;
- a. For BWR/2-6 analyses goverred by 10CFR50, Appendix K the decay heat power * -
valocs derived fror the Proposed ANS Standard shall be used as evaluated in sections 3.2 and 4.1 of thfs document.
- b. For BWR/6 analyses not governedby 10CFR50, Appendix K the uecay heat power vth: d:ri::t ' :m th: " :::::d ??.! Stir. died th !! h :::d :: : .h::: 'r.
Sections 3.2 and 4.2 of this document.
- c. For BWR/2-5 analyses not governedby 10CFR50, Appendix K the decay heat power values derived from the May-Witt curve shall be used as evaluated in sections 3.1 and 4.3 of this docu. rent.
1.3 The identical decay heat power values shall be applied for all reactor conditions and events, nainely; normal, upset, emergency, and faulted. 1.4 The decay heat power values in this document are based on the shutdown of An infinite thermal reactors fueled with Uranium (U-235 and U-238 mixtures). irradiation period at maximum reactor power and a recoverable fission energy of Neutron capture effects by the 200 MeV/ fission are assumed prior to shutdown.These assumptions result in conservative fission products arq not considered. ( decay neat power values for BWR/21g plants containing fissile an ru and coersting at average neutron flux levels <5x10 neutrons /cm2 / fec. and average fuel irradia- . tien < 20,000 hours. 1.5 This docueent does not specify Dre-shutdown energy, delayeo neutron fission energy, sensible heat release 'ran toe fuel or any spatial districation. e f ;
;1 O
'i 22AS792 sn. no, j GENE A AL $ ELECTRIC wuctsAn ewenov omsson 2.
APPLICABLE DOCUMENTS 2.1 GE Ooctanents
- a. G.J..Scatena and G.L. Upham, " Power Generation in a BWR Following Nomal Shutdcam or Loss-of-Coolant Accioent Conditicas", NE00-10625, April 1973,
- b. %neral Electric Company Ar.alytical Mode' for Loss-of-Coo' ant Analysis in Accorttance with 10CFR50, Appendix K," NEDO-20566, January 1976.
2.2. Codes and Standards -
- a. Cooe of Federal Regulations,10CFR50, Appendix K.
- b. Preposed AMS Standard " Decay Energy Release Rates follow'ng Shutdown of
'franium-Fueled Themal Reat, tors", October 1971 (revised October 1973). .
- 3. DECAY HEAT POWER CALCULATIONS 'f 3.1 May-Witt Curve (Ref. 2.1.a) -
For an infinite irradiation period at maximam msctor power the fraction of operating power emitted by radioact ve decay heat as calculated by: i
- a. (t,) = M (t,) + HE (t3)
- l whert M (t,) = fraction of operating power due to decay'of U-235 fission ;
products. , HE (t,) = fraction of operating power due to heavy element decay. P, = maximum power level during reactor cperation. s t, = time in seconds since operrtion (cocl down time). i i For the approximate fraction of operating power due to decay of U-235_ fission products:
- b. M (t,) = A t, where the following table gives the values A and a, along with the appropriate time intervals. !
I l l i O
, . n V 1 N '2 m '* 4 l GEN ER AL $ ELECTRIC NUCt. TAR ENE AGY DEVm04 y { i cottST1.NTS PCR Ft1CTION OF OPERATING P06*Et f- l i, - i l Applicable time A a
-interval, see.
.0603 0.0639, 1 71 5 e < 10 1 1 2 .0766 0.1507 10 5t < 1.5 x 10
.1301 0.2834 1.5 x 102<t< 1x 10 6
'me fraction of pcuer f ar heavy element decay is ;
- c. KE (t,) = P (U-2 391 (t,) + P(Np-239_) Po (t ,) '
Fer the fraction c3i operating power due to U-239 decays <
- d. P (U-2 3_9 ) (t,) = .0025 ,- f t, I
. i o 2040 k . . . .
.:.... :::: 1. a..
. =. a u-4==:. :f c:.: ::=7 ==:=: f a :.=, .
and initially the U-239 contributes .25% of the operating power level. Tor the fraction of operating power due to Np-239 decays i. P(Np-239) (t*) = .0024 - *
-{t s T
P TvC,000
\ l ,
where 290,000 is the mean life or reciprocal of the decay constant for Np-239, and isitially the :.p-239 contributes .24% of the operating power level. 3.2 Proposed ANS Standard (Reference 2.2.b). For an infinite irradiation perio." - at erian= reactor power the fraction of operating power eattted by ' radioactiv. decay. heat shall' be eticulated by:
- a. P,,,,,, (t,) = K (esI M ("s)- + HE (t,) ,
P Where K'(t,) = Multiplier def tr.ed in sections 4.1 and 4.2 M (t,) = fraction of operating pcwer due to decay of U-235 fission products. , e-9 4 i
# e8' s
, , , . - . - , ,,- , - , - . . , . , , , , - .-~r- ,
~. .
G EN ER AL h ELECTRIC 22AS792 sw. no. 5 NUCLEAR ENERGY DIVISIO84 1 mav. HE (t,) = fraction of operatir.g power due to heavy eiersent decay. P = .naxinus power level during reactor operation. 3 t = time in seconds since operation (coci down time). g '
'~
The Pmposed ANS Star.dard allows using equation 3.1.b to calculate the approximate fraction of operating power due to decay of U-235 fission products. However, in this document the tabulated decay heat power fractions M (t ) are used as reproduced in Table 3-1. s The fraction of power for heavy element cecay is: ..
- b. HE {ts ) = P(U-239) (ts ) + P(N -239_) (ts )
Where the fraction 9 of operating poser due to U-239 and Np-239 decay are:
- c. P(U-239 ) = .456 (C ta) , (-4.91 x10 t) s P
o iE q
- d. P(?p-239) = .434 C ta 1.007 e (-3.41 x 10 t,) -
P iI f i 007 e (~4*9I
- I t)s i
and the lattice parameter from reference 2.2.b for BWRs is approxir.attiy: f C ta = 3.28 x 10~3 1 YI f Re7 S
~ .
e
- 2A5792 W. 6 !
GfcN ER AL $ ELECTRIC NUCLF.AM F.NINGY OlVl88085 g f. I TAILE 3 1 % F3CT200tD AIES FTUCAJtD (Anvised 1973) FISSION F#GIOCT DECAr !!' EAT POWER TRACTIONS q IFFINITE REACIVE OFE14. T DIG TDE TISSION PRODDOT FIS3Ictf Paoco::T M GTM PC#ER T3W:"IIan COCE.DeG TIMR POWE**. I'RACTION c,, - :.onds 78 ( t,) t,, seconda M(t,) 1 x 10 0.0675 6 x 10 0.00566 .
~'
0 8 0.00505 1 x 10 0.0525 , 2 -0.0590 1 x 10 0.00475 .. 4 0.0552 2 0.00400 6 0.0533 4 0.00339 8 0.0512 6 0.00310 . 1 x id 3.0500 8 0.00282 2, 0.0450 1 x 10 6 0.00267 .1 4 0.0396 2 0.00215 , 6 0.0365 4 0.00166 8 0.0346 6 0.00143 s 1 x 10 0.0331 8 0.00130 , 7 2 0.0275 1 x 10 0.00117 4 0.0235 2 0.00089 , 6 0.0211 4 0.00068 . 8 0.0196 6 0.00062 3 0.0195 8 0.00057 t 1 x 10 i , 8 2 0.0157 1 x 10 0.000550 4 0.0128 2 0.000485 . 6 0.0112 4 0.000415
$ 0.0105 6 0.000360 1 x 10' O.00965 o 0.000303 2 0.00795 1 x 10' O.000267
- 0.00625 i
?
. - - . __ .e .
a . ( 22AS79z . m7 GEN ER AL $ ELECTRIC NUCLEAR ENERoY OtVislON REV.1 4.0 REQUIRE.*e TS , 4.1 10CFR50, Appendix K Analysis. For 10CFR50 Appendix K analysis the Proposed NIS Standard Describec in Section "J.'? shall be used with a 1.2 nultiplier times the fission product power valuu 'o. the total cool down period for all BWR/2-6 - plants. The resultant decay heat wer values for the first 1000 seconds of cool d*n are tabulated in Table 4-1. Interpolation in Table 4-1 shaii be done on a \' . ' 109 - log or linear basis. 4.2 BWR/6 Analyses (ezrost 10'FRSO, Appendix K) For BWR/6 analyses not er.vereed by 10CFR50 Appendix K. the Proposed AMS Standsed cescMbed in Section 3.2 sW1 be used with a 1.2 ruitiplier times the fission product power values for '.ta first 100 plier thereaf ter for coa'.iag times 10g seconds seconds. of cooling The resultant tire decay and heat a 1.1 eulti-ocwer values are tabulated in it.ble 4-1. Interpolation in Table 4-1 shall be done on a log - log cr linear ta;is. 4.3 BWR/2-5 Analyses (exce t CFRSO, Appendix K) For BWP/2-5 analyse <. (except late BVR 4/5s) not govermed by 10CFR50, Appendix K, the May-Witt curve described in Section 3.1 shall be used for cooling times six104 seconds. The resultgnt decay heat power values are tabulated in Table 4-2.
.% coolino tire; >1x10 s107 4 seconds the decay heat power values specified in Sectico 4.2 shall be used. For late BWR 4/5s analyses, specifically Limerick 1,2, Nine Mile poinz 2. Shoreham, Susquehanna 1,2, Itemer Bailly, and LaSalle 1.2.
the decay h2at power values specified in Section 4.2 shall be used. Intereola-
' tion in Tame 4-2 shall be done on a. lou - loc or linear basis. ,
s !
i
. . (. . _
~
i _ ;_mg _ , _a_ l , 22A5792 I N bI Rev. 1 Si. NO. 8 i , EtOt/6 ANALYSES APYLICATIQUIS(l) I , FISSICH PMDDCT and HEAVT EI2 MENT DECAY MEAT POWER VAIDES i DECAY REAT- ( FISSION PMo0CT EEAVY IImerT COOLING PONER VAIRES POWER VALUES TIFS POWER VALUES (2) K(ts) M(ts) EE(ts) P/Po (ts) ts(sec)
,* l
.osto .00292 .0839 o :
~1 .0810 .00292 .0839 1x10
.0750 v .00292 .0779 1x10 .0737
.0708 .00292 - '
2
.0662 .00292 .0692 4
.0640 .00292 .0669 .
6 I 00291 .0644 8 .o614 l
.o600 .00291 .0629 1xio
.o540 .00291 .0569 2
.0745 .00289 .0504 4
.0438 .00288 .0467 3 6
.0415 .00286 .0444 e
. .. . 2 .. nasoc a.,
.a3:o ,00278 .0358 i 2 !
.02s2 .00265 .0309 4
.o253 .00254 .0279 t' 6 (
.o235 .00243 .0260 t -
s 1x10 3
.0222 .00234 .0245 f
.0204 .00234 .0227 l 1.001 .0192 j 2 .0173 .00198
.00162 .0157 ;
4 .0141
.0123 .00147' .0138 9 6
.00142 .0130 ;
8 .0116
.o106 .00129 .0120 f 1 1xlo .0101 ?
.00875 .0013?
2
.cosas .00124 .00812 i s '
4 s
.00623 .00116 .00739 6
.oo556 .00109 .00664 {
s lxio s
.00523 .00101 .00624 f f i
.00072 .00512 t 2 .0o44o '
4 .oo373 .00037 .00400 00360 , 6 .00341 .00018 *
.costo .00009 .00320 a
e U 4 i i
. l 22A5792 g '
wws/6 AmAI.rsus APPI.ICATIONS (I) g ,g g, g, g - , rIsszca racoucT and tacAvr Etmaarr DECAY ESAT 70441 VAILTS , l 1 HEAVY ELDEDrf CECAY IUCAT co0I.Inc rIssION PRODUCT POWEA VALUES 70erER VALUES 70utR V71UFJ' (2) TIME K(t,) H(ts) MF,(to) F/Po (ts) tg (sec) ._
.00294 .00005 .00298 1x13' - .00237 f 2 .00237
.00183 .
00183 4
.00157
- .00157 6
.00143 - .00143 8
.00129
- .00129 1x10 - .000979 I
2 .000979 *
.00074G
- 000748 4 -
.0006P2 - .000682 6 !
.000627
- .000627 8
.000605 - .000605 1x10 - 000534 2 .000534
.00048i7
- .000457 4
.000396
- .000395 6 v
* .UUVJJJ i 0 .UUUJJJ . ;
9 .000294 - .000294 r 1x10 . t f I i (1) For 10CFR50, f,ppendix K analysis see Section 4:11 (2) Includes multipliers per Section 4.2.
-(3) Thes e values are not to be used to c.lculate finite irradiation values.
I I
}
r i
'b
..m , - -x., - , . - . . , . - - . .
,'t1
a = ~, , . _ . . _ . - - . . . .a I l 22A5792 FINAL
' Rev. 1 SH. to. 10 swn/2-5 AmAL t.IcArrows i1) I rzuzos Pmouer and uEAvr E:.Em:er DECAY MEAT POWER VALUES c
HEAVY EZZ1Dff DECRY NEAT C0 CLING FISSION P MDUCT POWER VALUES i POWER VALUES POWER VALUE3 ' TIME M(ts) HE (ts) P/PO(ts) t:(sec)
.0792 ;
o .0743 .00490 I 1x10'j .0699 .00490 .074d , 0603 .00490 .0652 1x10" .0626
.0577 .00490 2
.0552 .00490 .0601 4
.0538 .00489 .0587 6 .0577 8 .0528 .00489 1 .0505 .00483 .0554 1x10 .0495 2 .0446 .00485
.0393 .00485 .0442 4
.0366 .00483 .G414 6
.0347 .00400 .0395 8
2 .0J.13 .00478 .0381 '? 1x10 .0337
. v2 w .00467 4
00445 .0283 l' 4 .0238
.0212 .00426 .0255 6
.0196 .0040S .0237 i 8 ,
3
.0184 .00392 .0223 1x10 .0184 2 .0151 .00332
.00272 .0151 4 .0124
.0111 .00248 .0135 6
.0102 .00238 .0126 8
4 .00234 .0119 1x10 .00957 ; > I. 1 i 8 i t (1) For exceptions, cooling tires >10 4 and 10r.FR50, A00endix K analysis see Sections 4.3 and 4.1. - 4 I 1 l
RAI Number: 950.23 Question: Provide the test plan and the final hardware configuration for the PANTHERS facility. GE Response: 1 The Test Plan and Procedures document for the PANTHERS-PCC test is enclosed. The hardware configuration will be contained in the document " PANTHERS-PCC TEST FACILITY DESCRII' TION" which is scheduled to be issued on November 15, 1993. Similar documentation for the PANTHERS IC test is not scheduled to be available until mid-1994. f i' e s 28}}