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1 JAERI-M «ae««^o*a!kx*p^<03tffltt 197 5^3H ft H tt B * Ji ^ * W * 3r Japan Atomic Energy Research Institute

2 '.<7>ffi-S-#(i, BW.^flOTftRfr*' JAERI-M u*»? F t Lt, ^R&WCWfrL-Cv>& JAERI-M reports, issued irregularly, describe the results of research works carried out in JAERI. Inquiries about the availability cf reports and their reproduction should be addressed to Division of Technical Information, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-keii, Japan.

3 JAERI-M 6063 (1975f2fl12 BSD?CA vi-i p,k<o &fcm*mv>xkmmm&<dm?r&* :] f'm-tz> i&<dnm., mm&m ~ ^ T 4.2 fg^k«r^#«^-fk K a L x «: fjgss * * <, 6 f*y,_t ix#k^(e»lti mm ip^kttli^k, ffc^r, *-<i> I- ^#^ ^TV*"t ifflsobbsfco^tr ^-^ J:v» Systematic e $g; -C h njfgtt^ & & ^5 Cit^LtlA^o

4 JAERI-M 6063 Applicability of the Density Coefficient Method for Large Fast Reactors Tsutomu IIJIMA Div. of Reactor Engineering, Tokai, JAERI ( Received February 12, 1975 ) Applicability of the Density Coefficient Method ( D.C.M.) for large fast reactors has been studied, with the density coefficients of FCA Assembly VI-1. The method is to predict experimentally criticality of!.!f 旦 < giも,~n ir^w»n r~actor. reactor* eoeffiden~ usin<* the density coefficients obtained by critics! experiment. It consists of two steps of extrapolation; i.e., core composition and core volume. For the former, accuracy in the criticality extrapolation is excellent. Criticality can be predicted With accuracy of 0.1 %Ak ( 0.3% Ak including the reactivity scaie error ), even when the~ ^reactivity 士 'eactivity change due to composition change is over -30 % k/k. Criticality can also be estimated for the core volumes about six times as large, with practical accuracy.

thod ( D.C.M.) for large fast reactors has been studied, with the density coefficients of FCA Assembly VI-1. The method is to predict experimentally criticality of!.!f 旦 < giも,~n ir^w»n r~actor.

5 B & 1- ^ Bra 1 2. &g&g«^g 1 3. FCA vi-i m&ftk&i&z> m&$i.<nm'& FCA vi-i ^-^ft^k^sra^aipes^ftf-sij^oaffl 5 5. # n tr-ttf 1 6 m s? 1 6 #:% SK 1 6

6 JAERI-M fissile %%.<D%g.<D&V>, <CC7-;H> = *'AaJfc Slffi7c^»^(A ^#*SI^6tlK*K) ertgiisa) ^S-^KIS^C i*4hiwlx, mmtfs, &m#>*mws&)m:tf<*&* $ tit*nm KriSffi-t^/tto r*-4/i;*j &«3 4J. &S$* **T VT'-P** FCA vi-i F'D l2) r K^jH,ffl ie<*s*is«>*t^*o»l^*ll^-t#%aj6ffl* I^^4^n7to vi-1 #3,k W: a K 5-f ^-4W-3 2^j^/->'fiiCi.-e*s*5-5 i Jt h y'-vffififctfe'ft ffigfcf'h A fc O ^ X Id mtt.tcm.!& S * % * ^ 7- JHfe^g tffgr&tfcri* lb B ffi7c S?t»J ftfc fl"st L Jfc'l 1 SKffi^^-^-tt^#4#l^ iab3cs^(is*t1-scfskm^'fk^%^& (1) KfSo?feo Cht,vi-1 'F-D K^ %ffl^tx3i'f Bg^tt% : f'i»j-t?>si-&«ffi^. SfflnrffitEH^fc-on-cfiMffl *^ftf^-: ft4^^^o * * *. :M> y * A ;% (] Pu-u ^-ft^«s^cil!g^^k:il-t-?>p5& H ix^i: -i s-c<oiiif/cj'tt VI 1 '^ ^^ iefiifsfflrtk * 2> t #18 <b*ic 4 -o 7fc 0 $igfclis2-$rstmsffl fs, i3$tf0a VI-1 «ft;ic *!**& && 2. MM&«MS ( 1 ) "Cffc^i'^i*' I- -"' ( assembly vector )% Ml,

tcm.!& S * % * ^ 7- JHfe^g tffgr&tfcri* lb B ffi7c S?t»J ftfc fl"st L Jfc'l 1 SKffi^^-^-tt^#4#l^ iab3cs^(is*t1-scfskm^'fk^%^& (1) KfSo?feo Cht,vi-1 'F-D K^ %ffl^tx3i'f Bg^tt% : f'i»j-t?>si-&«ffi^.

7 JAERI-M 6063,-\ ~* k(a)-1 k = k(a) or p =.p (A) = i 4; (2) k(a) %i Ml&ir.#m%&.Z> iikij Z<K> >bi)' b <nfi*,li~>% Z> Ci*tta5 a AS In "CIS km ST, (3) c tmzimwkwt. (fcm%wt. &i$z -JE.K LX &&%%*_ ± t. t Kf&&$.ft: go-go dp M k =! (4) ffifrmrxbt dp = 2 d. C k>m dnk k > m + 2' M k dv k ( (5) ^P (A, -X B ) = jo (A s ) - /o (1,) = / j ^ mc k i m dn kjm + M k dv k } (6) Slfflproceaure (<±&w4a <-?& ( Fig. 1 ) 0 t -f, Es^Sl^^fi* 5 #:* i T$IJ -gn ft^m^w^m^xwmt V, 2 2ffl$fc"tffcl$U:f%ft^2<7)%<ofc:g:.!L7fci: # 15 lgg -fb; (<=>/<>') *#*> (*H fl.#), Jfclc«fi6g2ro-t-i#:^*«iii islii-4-e^it«-a-jtt Kid 1 1 ^" = -kv-tt ~2,» -<>.-- = (9) Ol##*%o y' y >"<r * <nmis.» (?- ' it l^tt k' Xttk a <D WLVgX-, shape factor ^tt k s o SPg i? it'll: it K i t -5 # tiiei- % #- ««*:?: h ^ K U II^M/J- 5 v» 0-2 -

& ( Fig. 1 ) 0 t -f, Es^Sl^^fi* 5 #:* i T$IJ -gn ft^m^w^m^xwmt V, 2 2ffl$fc"tffcl$U:f%ft^2<7)%<ofc:g:.!L7fci: # 15 lgg -fb; (<=>/<>') *#*> (*H fl.

8 JAERI-M <=? (1) ffl#fl# Fig. 1 Procedure of D. C.M. ると 5> A: 白 exact xac~ perturba~ion perturbation theory X l/i. * ft-»2 = ' -J- 0+^F&> - <^+^A(S 2 > <<V^2> て係数の変化をと b 入れた" 曲線外挿 "を行念う ~で臨界実験を行念い測定される密度係数 ~.! + grad^dgrad*) r*?, 0 Lfc*' ot, K^5 J: 5 KH^JlK ( ^ift ) 4 ^&ffctt#j JffliOm, rc#lfc id <«: { #* SRtntf** s (MSr«, * *, -e*- * -*:#*.* )o fcfc ZV *>1 M* X* ''T- -W- > -~-»-i- n /-i r_^l_ -l_ ^ -. \ \ 会会 A 珂 J 制 n 辰野,-も~) / _^L_~±-'_ U('J3KI'-»MII-»] i^ t- «J. "in "mi ^ r "^." is J/ v. ; S."a^ J [KttLXirt. Cm = c mi -= ~, 品 Z aa (13 (t~ o^^;? のスペク h 山 /HIS- 内び #!?&# * 随伴スベクトルでの "«* h ^t:om^ SifM^<o^sa.t ^i*^*3-to m 物質断面積の双加重平均を表わす V^fco^ttt lesiictt iteration ^s^g-r* So X, ifesl*3 K: o^-ci'.i^sfkttt&sljlbgfl-ktfc-h- ^ / ^ twits'*tr*s^do^-fb^^t を掛けるベきであるが百の変化が大き < 左 4^: rctt&«{im& #K い場合 κ は密度係数自体 K 瓦 A/lfctti-t-t /~を掛けても Ut4 大き念 ~K ついては *) a ^D = 1 Atn A"t = -JD^.Jjt,,,^,, 3A* 3A t 32 t n"atra 3-

$, 0 Lfc*' ot, K^5 J: 5 KH^JlK ( ^ift ) 4 ^&ffctt#j JffliOm, rc#lfc id <«: { #* SRtntf** s (MSr«, * *, -e*- * -*:#*.* )o fcfc ZV *>1 M* X* ''T- -W- > -~-»-i- n /-i r_^l_ -l_ ^ -.$

9 J A 60'~ «B! - u A o A き 5 S^o <l])#.k&'s>x<v<if>/k 1 - O a > = Ot> i*<t,,~ セ'~r + τ 一 (-~ -TE7 - " < a > < l > + ~5T~ ( "^ " 1 } と~るので, 核分裂物質 K 対する補正係数 fm = I '~ isso <fft>. <vo t y/y x folk * i $.frwk*fav.wfo% i A^S-tf"* *^*' JtV* no fis sion sourcefigfl-icifctflji-fco-c, $kffl>wr'&&%:frt> g,k f m # * J6?, H S 0 -< fl a > f± RiRf 3&. &ffc^ fission source Jil.^.OJii 5 T %^*pi" 0 (2) fth^# fto^^ -y T-Cfes, mm* 2 K Lit^mx^,b#^* mti-^'p'btx'ma.±k Jog " Mft#"*?T4 9o ^JfcftW^ffcKftL-C'feiESiKtofl-lffc'fTttS feto "noraalized edge mass coef f icienx ( ffifeft mm'm.m^w^ ) " B % & fl < < m Ltfflk % 0 dp dv B kv (19 d/> = dk/tf <D df {& f 5 t dk k dk / k = B V tr± B = / (1(3 dv V ^ f i m dv/ V c<r> B ( xtt B ))i5tfttloi^ft*%o IS^ftKow-ctt ~ 1 0 以 *JiL_h» 上. kfeko^-cti 3 ~5 oin*5«iiii^»h»if^2)ifflilis>ti:4v>o tntt k-vft jjs H #:ffct <o kfir^te-fb tx Li #-tt iwffi<nm <a&wtfx : '&afjl83 ft5 c iki5. fiasfl:^ ~の精度で求める乙とは鴎難なので計算値を用いて外挿する帥式の B も ~ k, _ k T O P(V 2 ) _ P(V ) _ V 2 B :<-i koopcv,) p(v,) v, 昔 O 日 J: き註 5 K K V, 関 t 係 Vする 8 "T 断 «面 non-leakage 積の誤差は大部 probability 分打消されてしまうからである P(V) Wit«0 ^ #!!{& u 司式 L K, よvob t 体 -*? 系 ~の <J a <D SS^ttM*** %o HltlKI!)*»5Ktt#:i V,, V 2 -co kflcoft^ji.^ tannic i & * to & o - 4 -

$m^w^ ) " B % & fl < < m Ltfflk % 0 dp dv B kv (19 d/> = dk/tf <D df {& f 5 t dk k dk / k = B V tr± B = / (1(3 dv V ^ f i m dv/ V c<r> B ( xtt B ))i5tfttloi^ft*%o IS^ftKow-ctt ~ 1 0 以 *JiL_h» 上.$

10 3. PCA vjr-i M&m^*$tftz>'m&$&mm {8) *i6i 5 k?% m%ntt&z n<o &*Fk&foKfrfc^x~MK 'p&it-$ititm& t?^ h /-yfl^klftlft-t^ *-^ ( VI-1-S2 & # )r*5* KK JC ilf^h/ 4 PCA vis & MfS<SMS *8i«#M*?«!^ itffl?mft)fftfie% Tatle 3' IC^-f (2, 0 M ^ y y? ^, h ttrafgj'jf,6w!s##ft Ji ^ t*5o 2j^7cR-Z K J; ^RMfB+Wi^^ffB^it^^^^tofc ships factor = ZmbxX&M&ft$tli± g biho J-F-D -fe.vh<c Jt *, k eff 3tWffitt tr - y ffi#r'fr &«i&&#*ifcih>k:*»fcfrfco Table 1 K vi-1 $ &#:ra * ( **-to 4PJSoS?^KoiA-cttgiJ 'S- g (3) K:a5'<ibti-riA?, 0 ^K^«*^/^*fi:-eft«a-fjfe»«ft#J@ ( 7*>\ -V* t ) <DmbX mmwl (1) <Dm%im L6ft,*ft3 fiia ( J_F_O(0.546 ), RCBN(0.537), A.B B N ( ) ^fl ) K* L^ h *-^T Po* 8 L* ( ft = a04 7 5#^/k ) 0 tr/o 0 tt /«9 - # 0-50«i^hp- *IC*JtE $ fc&8&=» - KSIMPLE-D (4) >t Jt SftStffl fc i % K^-f 0 it»fittt J-F-JT* * h #5! ifeffi 3*S*fit##:«( Table 3 3 #P8 参 ~('I ) JC**-*"* 4 or, tffett k = 1 KttfE-tSNU 7-5 y^- y h ti&m&fovcti-tz 4 0-C*5, Table 2 if), t(kpu-240, Pa-241, H-238, sus gc#6. < * u c. i i)ifth-!3ig *sfem'r)*s^<d4 3 lcw:s(bs- x '*' ^ ISMWA otlflslrtii, -tftttt 1 ~ <&&!. 程度と考 33*. えられる bilbo -5-

$, 0 ^K^«*^/^*fi:-eft«a-fjfe»«ft#J@ ( 7*>\ -V* t 0-235 ) <DmbX mmwl (1) <Dm%im.1 1 35L6ft,*ft3 fiia5 3 94 ( J_F_O(0.546 ), RCBN(0.537), A.B B N ( 0.$

11 JAERI-M 6043 Table 1 Composition of Assembly' VI 1 (lo^/cm?) Ma~er1al Made rial Gore Blanket, (Tost z one) C B.U. ) Pu Pu Pu-2 41 a B o 'i 6 o H IT M a S 6 Al Or a i P e N 1 a ~ Table 3 Critical parameters Asse~bly of Assembly VI 1 ( One region core DU blanket ) Expe ri men t Calculation Core height Core radius rad~us an cm Core volume I Equivalent sphere core vol urn e^ 4236 I Blanket thickness 2 2 cm. k e f f e c t ive ( J-F-U) (J-F-O) C RC BN ) (ABBN"} >)c Shape f ao t or =

6 6 5 2 N 1 a 1 6 3 9 ~ 0. 0 7 9 6 4 Table 3 Critical parameters Asse~bly of Assembly VI 1 ( One region core DU blanket ) Expe ri men t Calculation Core height Core radius rad~us 9 1.

12 Table 2 Density coefficients of FCA VI 1 core (Ak/k/10 2 * atoms/on?) Ma t er ill J -F-H J F-0 BCBS* HOBS 3** ABBS Experiment I ; Pu-2 3'.' ± 1.5 i=u-2 4l] 6 S.O E dfc 3. Pu as ±15 U -23: ' ± 1 U Q ± Q ± Na 1. S ± Kl ± SUS ± a 0 2 MO ao 9-6,8 Z I H< Original da ua ; BNDF/I3-I jjcf: original da ta ; ENDF/iS-M

1 ' ± 1 U -2 3 3-9. Q 6 1 0.3-1 0.6-7. 7 8-7. 1 6 6.3 ± 0.5 0 1.1 3 3 1.0 2 2 1.5 8 8 1. 0 3 6 1.8 4 7 1. 8 Q ± 0. 0 3 Na 1. S 8 6 1.5 0 0 1.9 6 7 1.5 0 4 1.9 2 2 2.7 3 ± 0. 0 9 Kl 0.9 0 9 0.

13 J A E H I - M ,! 45o Wlt fl3&;&fc Ltfcte<73* s 'D'#flM2 3i<J*, 2 2 an Wft-tt? 7V7'7y^ * timm fifsi-ioms-stt vi-1 i: B)D), r*> ^ D * j ^rtw'k 'ffifes'f'fr,?c4 vi-2 * &&-r;* h /-y~ l m$.! ip>b, *-I?>"ffi#Sfllfefii<a*;&ZPB-VI Assembly *7-C*5o (i) r^i^j Wfinj^o 外挿の対象として選んだ炉心はも A..f じ ~~J fissile Pu$$^fcfg V»-C l/^ 5 <0 IC *t L fb^c^j 11(1801 fissile Pu %Slo-C* > Table 4 t ^ft#»i ( R CM. ) C X %&% &?%)}&%.&* $ ntv> 2> 0 R^iCfctVI-l #(c i s RfcffisEifc (ftmiti- Jto^sSfg), KiS^^-fK^ <b(7)^:-e^a6 7tn: eff ( R)± ), & Xt>'aireo-cti Sfctt- K k e f f, M^#Ki 5 *tf> 7cgg-!rM:##*3 fix V> So tf^fltt ffiie^sfm tt vi-1 *>XO-'VI-1 fc W\fcm<n r4a/d*j ftw-kk o^rmfctt^ftfir 4^ft8fr ItfO^CttfEo-t^tofc %<7)-T 45o Taolra 2 KTfft VI-1 :jp,[j.<73 $Jgj&2 &Ct <Ts f m % tfh-t VI-1 - r4,a,d^j SiJSI^^S?^ ( *=) )&&&& (St^fi*-li>*5ll8fl ) fc Mif>^P ~ = i C m f.^n m Jt ^JxlGK^tSr^ftfto CoKEKaEfk^ibS f.k(7)*k X & k e «in ^SiEffi^ftfctSIJ^W ±0.1 6# ^H/k(cWUt^fItt ^ ^>k/k T^K 10 AlcAioftf^So»J fctie t. LT Pu-2 4 0, Pu-24 1, U WffifS^^K vi-i r,c,"frs!tm-r^ n>a,i;*j KWF &$.!&<?>* * ftwfiwdirect^miwkx %ff K^ LD. C.M. (C I%^(.#fl(l C^wMtt C*5o WCitt aam. K xsffleg;^#oiaffltt3isg.^e: t%*l-ci«a a^icx 式 K 工り 0**i«j*t7t#fl ^-#jc 求められた体積 9~ 挿陀 %Bgff#«m»fIW: 6 73 ± 7. tr*^o tm^^kttrisffi^ >-- '^<r,mm ( ± i # ) tt ^M^nt^^7i^a^#Kff si^tt^j&sft-t^s^o -en*5t^.-ci,ismtt±i o^i (2D ffea/d^j rtfljjp/ij VI-1 ^C, TiA/C^J F'J'IIW'k'^fl-^S* Table 5 K^-f F^flJ* 3,^ <T> t issila JE< $Um * fissile fe IK *t LT Id 1. 5 it^'o-x 4fig It * < tv> % 0 C. /' ' ' T I-1 fflsfc と内側炉心組成の 1111 の実効的 ( 平均的街度係数が '1 I-1 組成での密度係数 (}JllúV~ 約 1. 5 倍 ~ -8-

.f じ ~~J fissile Pu$$^fcfg V»-C l/^ 5 <0 IC *t L fb^c^j 11(1801 fissile Pu %Slo-C* > Table 4 t ^ft#»i ( R CM. ) C X %&% &?%)}&%.

14 Table 4 Prediction of critioality of MOM JO OUTER core by Density Coefficient Metnod (D.C.M.) 1 Mil terial m Core composition (10 2 Vci» 3 ) N a(vi-1) ".(MONJU-O) <^-N m Correction fac tor 1m Reactivity change (#»&,/k) J F n Experiment Pu Pu a a ! ~ Pu U Ka hi sus a // // // ~パ Total! -a435 -! 4 2 ± a H f D. C. M ± CD *eff* \ 0.9 i 64 ±0.0018** Ei reo t c al o. I Critical vol uai e i- 7 I** %. For VI 1 core volume (423.6 ). Keff (D.C.M.) ob~ained obtained by Eq.(7i sfcfc Including error of reactivity scale

3 2 6 1. ~ 1 1 4 Pu-2 4 1 0.00160 0.007831 0. 006231 1.1 2 6 3 39 5 2 3.3 0 5 0-2 3 5 U -238 0 Ka hi sus 0.001516 0. 0 0 1 3 0 2-0.000214 0.69051 a519350-0. 171160 1.5598 1.3410-0. 2188 07656 0.

15 Table 5 Prediction of criticality of MO N J U I N NF.S core toy D. C.M. Ma terial Core jmpositian ( 1 tf 2 /ca? ) Corrnotion Reactivity change (56i^k/lO factor N m (MONJU-I) &Ni (VI I-iMONJO-l) J P H E;xperimen~ Experiment CorrRc~icn Reac~ivi 吋 change Pu-259 a Q Pu a Pu S U a a n a a 1 i U Na A a II n SUS il T otal -2 a ± ± ' 5 k erf > 1 Direct calc ±0.002? Critical cri~ica1 volume 1903X ± 4 D T * For VI-1 ooro volume ( Z) >(ctc Including reactivity scale error

549 Pu-2 4 0 a 0 2 3 19 4 0. 009194 1.4 0 0 9 0.9 5 6 0.8 0 4 Pu-2 4 1 0. 00S799 0. 0 0 4 19 9 1. 4 2 4 1 3.372 2.820 U -23 5 a 001400 a n a a 1 i6 1. 5 1 8 2 0. 044 0.041 U -2 3 8 0 0. 55989-0.

16 JABRI-M 6063 i^tiflicti^t-rioswtsj*, &#& Lx <nmfc& it±mi& t t^kshkx^?4> Table 5 *>» C, # X 5 K«J6TiftgE I < Eg^ttt fl.#tij3fe 2> e -* * to^, VI-1 *p,frffc.~κ 対ナる内側炉心組成の孟 ~j. f?>^#m ite-fjj»a0 7* ^kl^&to*l/» 0 O~ -3 0* -ak/k ^KiS? 'ffe;rc# L"C 4, tossl^j * <4*#ffl** ^ 5 C fc-p&so ^Ifeffirci: 2> k e f f fltt ± ( s&**---«' isi *#jr*ixtf±o.oo27), ftffinfakxz>$,r j e?&mmift 1872± 4 0 ^tr*5 0 (3) FHA VI-2 #3,fr <5> tixfo. "1>-'v D^J ^fijl^ijio^il^*» ^ 7 " > 7X2>Z>?CA VI-2i^#Of.nh/- J-ISfiic X 9fiic6 -mm^^^'l^y' 7 * * *, * fct^1-1 <F'& i K ««, CI-1 * <b vi-2 ^O^i#gS4 Table 6!C^-t 0 ft *< >, -? *H^tt [Ui:*J rtf!if4j«ii- rk: ^o VI-2 'Jp^if-g-, jfififcgeffci LTTtt9 2~ 2* fissile Pu mmm 3): 1 ^ ;?s > 3 *fc#» t> 2 枚 tfek^e ''C~!:Iスベーサーとして.x-c- * _ t-c A Al 2 3 0o S 3 ( 1/16") 1 ##flnfco:fc ttftratfflj W4f!Sifc1E ffi Ktt&l/> 0 D.C.M. jc X h VI-2 'ip^is^^fs^^fstt ±27 /?*% Cfflilflx (4) 3PR-VI Assembly #7< 6 > ZPR-VI Assembly #7Wt^ j'#^sw VI-1!p<l>» 6 <gjm_k 4 & &, X, Eg#l:OSlJ^fI #fc* c tf»feft«w#4^to &* «&& ««*!: ^~ * ^Kttf&«?0!^,C-r*4 0 Table 7 C 71-1rf»fr,ASHemoly # 7"«0«#ef*Sto * :F, ffils^lflclil Ltti, J-F-H-fe > Utijnail. t#ft K#L direct JSgtffWfl < ScU-C^% 0 cl/k~てもがよぷ -3 6* ^k/kjt 4friiXt4S(5tSfti*l4 犬き左反応度変化と大き左スベクトル ^- 1 * H ^-ffc^ig-s 変化が予想さ nsk4**toib-/vi-i o ffi^^r^ii,e«gtc^.#ai*?>c:i:ttjis^6<)-c*s 0 HI*file x 2> kaff W ± C*^ o Assembly * 7 gg?jtfg!&k X%gi##:1» rtt-t* k eff ft«d.c.m. nifcfgid: a994± 0.004? * $>#8W#4 5-4 <ft^-c^s?; #3-*o -*a^p«iffg%*^feto4 23.6^ (71-1 #;» ) 6 1 Q, 9 3 5, ^, 2286!!. 28 6^, との oriojfak*^l5: 聞の周辺質量係数 Bwlf^Cf: の計算を.TJ-P-Ei -F- liと ABBN 珂 p-t セ.~トで -y mfi4lrt#mfo 行念 IA 各体積での keff %*K)7to * *% Table 8 K^i" 0 pj-fc-/ MH "Ctt*>» 4 & H # S JW [f^ft is5 -b* Miao^fC < f>-<n««its-«c*5o ABBN ttjssit^k: X2>eaf #fl ft20 4 7^ i. j_p_ I I r a K < b-< 2/3 SgEntHiift & l^ 5 ffiffifc * w H?%%7fei6-t?*>65^, ttlt4 VI-1 O 2<g-JM±Of$^-C*% 9 35^ KfrktliifWitt 0.5* ^k (C*"5-i o -r^% 0 ABBN vc ti, Bi^i^ii #7 *F,fr#:;ffK:*>-</tfc D. C.M. HifcfStt ± L^LUJgft^K: * ( J-B'-H) ( ib3»)osk< fe^ttttttfc ^cc/hs^o ^56i-%*n < B L-ctt J-p-nic xstt*fflv»5i?j^as-c*%o ftflwwi ^WtttSC-t» 4 <nr *?> **, M^usv, -crah^g^fu U-riifiRfl-ffKX SfSlfcliK Si!->rW5iC5K, #*»^1$ 4 to*i :ifi«lft4 gftfttt f-flljic -> X &&&%.& <r>m&v * ;& ro-z? $, > 0 の計算 { 直結 dir 白 C l; 拡散計算値 'C 対し D

&mmift 1872± 4 0 ^tr*5 0 (3) FHA VI-2 #3,fr <5> tixfo. "1>-'v D^J ^fijl^ijio^il^*» ^ 7 " > 7X2>Z>?CA VI-2i^#Of.

17 Table 6 Prediction of cr iti caliry of FCA VI 2 core by D. C. M. Material Core composition ~ (io'vrf) Correction Reactivity change (4&ks'lc) ~ôk/k) factor N m (VI-2) ^.Nni (VI-1-+VI--2) Hi f m J F 31 Experiment Pu Pu Q3 8 7 p u 24 1 O00 1 Oi? U U Na A [> it 0. Q // SUS To ta L ±0C7 =~~ a ±0.C006 k eff 4 [ Diract o a 1 c ± a 0 " 1 Critical volume 1813/ 1710±27F^ ^ For VI 1 cere volume (42 3.6/) ^jof; including error of reactivity scale

406 0.342 U -2 35 0.0 0 1 5 1 6 0. 1. 4 4 6 3 0. 0. U -2 3 8 0. 6 9 0 5 1 0. 1. 0 0. 0. 0 1. 7286 0. 1688 0. 9 6 6 7 0. 1 8 5 0. 2 9 4 Na 0. 7 6 5 6 0. A 0.24029 [> 1 0 4 8 7 it 0. Q 9 2 0.1 6 0 // 0.

18 Table 7 Prediction of criticality of ZPR VI Assembly #7 by D.C.M. Ma te rial m Core composition ( 1 0 z 2 /on 3 ) N m (Assy #7) AH m (VI-1 -»Assy #7) Correction factor ~L:>k/ Reactivity change (<,alc/lo 瓦 J F II Experiment Pu-23 9 D Pu Pu U U ' N a ht SUS i a n n it Mo (calc.) To tal ± k f o r r n c M ± eff VI-^1 core volume ( ) J [Direct calc * f o r fceff Assy #7 core volume ( '9 4±aooi y*^1 C ^ Including error of reactivity scale - % 3035 (Cy linde r)xu.85 (Shape factor)

5 6 1 2-3 6. 208-3 5. 377 Pu-240 0. 01178-0. 00222 1. 7 6 0 5-0.254-0.213 Pu-2 4 1 0.001341-0. 000259 1. 5 5 9 2-0.224-0. 188 U -2 3 5 0.0 1249-0.000237 1. 6 5 5 7-0.1 0 9-0. 1 0 3 U -25 8 0.

19 JAERI-M 6063 Table 8 Comparison ~ of volume extrapolation with two 官 o different Edge Mass ^efficients \~..,,,, fficienth (J-F-jj; and ABBN) in ZPR VI Assembly 47 composition *** \ - Core volume 4 2 ii 6 I ? / 1546/ I (VI-i) (Assy *7) * Direct c a 1 c. k eff (J-F-II) k eff (ABBN) Experiment (II C.M.) *eff ( a/j-f-i) k e f f ( B/ABBN) ± ^ Critical volume : 2967 (j F-S) and 2047/iABBN) >f fc Including error of reactivity scale > o(oj< 3 0B5Z (cylinder) x 0.85 ( Shape faciei) TS"1J 9 Comparison of k effective valuss for VI 1 core volume Cere composition keff ( J - K -1 ) D. O. it Direct c -\ 1 o._ M0NJU-OUTER MOMJU INNER FOA VI ZPR-VI Assy #

8 16 0.8 8 4 0.9 6 0 1.0 15 1.032 eff (ABBN) Experiment (II C.M.) *eff ( a/j-f-i) k e f f ( B/ABBN) 0.7 3 1 0.7 8 6 0.8-19 0.9 2 0 0.9 6 9 0.9 86 0.7 9 3 0.7 3 7 ± 0.0 03 0795 08 5 6 0.9 2 7 0.

20 JAERI-M # m ibti^tw^^k-ohtfi L-C*5 0 VI-1 iip-fr-*^ (4 23.6^) ~ tc*f^a^jlp/^iia^o 対する各炉心組成の k eff floh^jlstscst^cflt D. CM. K X W1ffS (V> "ft! ^ J -P-n-t-y h ) -9e* Table 9 C^-to 9 KM%<D-> gc7$*&^ ^ 5 itt^-<? h -^^ft*"'>5^ ^, fcsl^fi 9~ 示すとのよう K 両者の一致が良いという乙とはスベクトル変化が小さいのか,あるいは ^-t^ b /i^^#&^t%*;h. f #7)s^>Kfr?83nr^ ;5». l^fhk Ut i VI-1 S 5 -k-e ^-* ( S?K^iSt )*bto:5k5t <W# «*% «: JE*«^T;&SJC 9 rcm» HSo ^# W^i. U-T^l^Tt'4 00^ ;jj 5 *> PCA VI-2, MONJU-INNBR, ZPH- VI Assembly #7 5 oojgf^jfr.* ^^ h ^ttiffislcjfiwot t Tfct 9 t> ABSOTI bly +7 ft'^tthtft5 Lt*?> Fig. 2 tc J-F-n-6^ h!cjc% VI-1 ^,jji Assembly *7 ^g-^ ^t^^ T? ^ ^ ^ h A- ( fundamental mode apeotrum ) TF-J-# ft VfrKWlJi Kti-frft t> H/4 5 ;bjp AssemDly # 7tti*V>, A, y 7).4^-<n ^-Cfc% i # #%o L^LFig. ~て 3 K^i-*n 示ナ知 <ffib ^# ft*9 組成外挿を行左う V VI-1 工炉 r<6#«ktt^&^^ 心体積陀対ナるスベクトルを h *- * 見る ii^if IC «- *!.«-;*;# 4;itet l~t t#*4o Fig. 4 «Assembly # 7 &1&"C VI-1.JF,fr ftg{ ^4 23.6^) fcbg#ft$f (29 67^) K ^ J ^ ^ I- ^ i f ^ M i i ^ t ^ C t 体積 ~423.6.e) と臨界体積 (2967.e) にかけるスベクトルを示すが意外と差が大きいとと #fl-&o J^± i ;*»&# % ttf*is* SEK Lfc* 4 MfiSc^i^O^i'Ctt ^ -< i" h»mt tt-ztlite-kg <tt4 <, Lfc#~>- *»$?& <B6fttt*fl.#fcb*?> tv> 9?fc& 0 Fig. 3~ K^-fSK ^'*^ 示す程度のスベクトルの b ^oi#fc"t: 差があ円ても «!$# ##-J-31^. 組成外掃が予想外に KfifEK 精度ムい < i^-cwwrttffio q ているのは級成の ^{kt i. 4.K«ge^*!t^^'ft-t%C t **> Aftfc " Slg^lfiS "& ±>75>4f "Cfe^o -*"** I- *-<^ h ^^ l^t^kl&aift.-c^'-c*^^ I- A.^KttiSfflffiH^Jtwtot'S^-'^K t, /*>?)> n> lb "fii 3? IllM *# * fcfc to fission source 1/k^j^4 fcttilfflfeb* ft 次 t^(c#:^^(.#lc ~ 体械外挿について Ol^>-C#^. 考えてみる "t * & a Normalized Normalizen coeffici6n~ edge mass coefficient B I l y t J-P-niABBJi * -y I- * *> ^ fl fi 5 ^Ki-oT#:aJt^A# («Kc«lf6K H^ta-C < %T>S, ABBK -b -v b *±B!#-S:4li^K:/J-'5 < jui S «S fttfs fc a T J-F-n-fe. y b K Jt ibtfflnjffliifgtfc^isolxso -?: $ Assembly #7 ft$j (!S ^S &f!) l/cti-fzx-etr W#f!tt ± t & tj -'p^^js^t fe % # VI-1 t AasemDly #7 の 0^l^K55!)* ^4#li;-t*T-WfarfIEL<^.^fL-ClAai:#^.fjti%o 非的質効乗の差を考慮すればほ I~ 正し外挿していると考えられるの ζ Htt, れは, 外 fl.# tbftj& 挿の出発点に r& 在司 o-ci^a ている vi-1 VI-1 炉 m^<d^nfom<dmmm.!ri.4tt's.mk* 心の臨界体積の実験値は非均質板状セル体 ^tt^rfti-a 系 ~ 対するものであるが, 4 -Claris, Assembly #7 -t^ ^^^K ^J^: ( IE ) ^ X ^ t ^ i «j H5 ^ "b?*> %o Oa&frb o^lkslflftlil-ti' HK: x-or'bkrm^iiiaoiich.'fcf'ifiksl'r Fig. 4 #p<ft fsfl-isogst*-* n*ii*4!)t5tn5 t *fb:*-cua fc&fonao -f**?*>085 $n< koo t non-leakage probaoili ty fg tgfe Lfcig-^-koo tfjftg}. HK$otLt^, したが Lfcrt^T 司て νσf s/a f や ^ 引 o^ 等 # f0f S の断面積も% B~てかな %*'! b ti 影 ^ft5iu5 響するというととが Hift(,H?io 考えられる -1 5-

l^fhk Ut i VI-1 S 5 -k-e ^-* ( S?K^iSt )*bto:5k5t <W# «*% «: JE*«^T;&SJC 9 rcm» HSo ^# W^i. U-T^l^Tt'4 00^ ;jj 5 *> PCA VI-2, MONJU-INNBR, ZPH- VI Assembly #7 5 oojgf^jfr.

21 JABRI-M 6063 Wf "ilffift" e^kttfnl^tt* <^^^* Eg#ttOffiKtt i Lt5lE(^^-*oa in vi-i r^^f,jii^t--t-<-c pu-a m^tmmn^ &&*M&&tip<D&ft#.tf±a.5 #fli. *;i:. "** ベクトルが * H *#I4 異 ~..,ていても ^-CIAT i^bs llis%07)»tr K:S5'& 相互の関連をつかむのに都合のよい (^ systematica El"t 自 fcffl&i; 6. tr -f <> ^Tfeo FCAVI-1!p,C??&g$&(4Pii jftj&na ft ip^mft^k II-t^iTi) fit,<,<<:-* O'RCBN, flobk'3 -b -, htco^ttf]? ft? ^a; ffll#c^tri^t Lfc 0 CCK&b±&X # f 1 tt (1) ^A &{& ; FCA V 'F'b&VZ&ft %>^&{%-M. JAERI-M 5890(1974) (2) AfflH^'fte: F 0 A V I ~ 1 ih-s-'ftoks^^fi, Private communication (JAERImemo ) (19 7 3) (3) U&, i t! FOA VI-1 %&foki?irthimfe{& L<Dm'&., JAERI-M 6062(1975) (4) # 3f5*= : ^TCiiifKt f S ^ t ^ - KSIMPLE-D, JAERI-memo ( 5V:«) (19 7 1) (5) ffii& # : FCA!+~ VI-2 #i&#!s?^ S, 合体の版界実験, Private communication (1974) (6) Till, C.E., et. al. ; ZPR-6 Assemblies 6A ami 7, ANL-7910, PP (19 7 1) -16-

22 JABHI-ll 6065 Tq q J-F-E 10* 10 - VI-1 Assy # Group No. Fig. 2 Fundamental mode neutron spctra of FCA VI-1 and ZPR-VI Assembly #7-1 7-

23 J A BR I-U 6063 i 9 J-F-H VI-1 (k #ff = ) Assy #7(1^= ) II J Group No. / i I Fig. 3 Neutron spectra of VI-1 and Assembly #7 for VI-1 core volume ( ). -18-

24 J A E R I M 6063 ^ J-F-I fl (k, ff «1.0) 423.6A (k tff *0.73l35) Group No. Fig. 4 Neutron spectra of Assembly # 7 for VI-1 and critical core volumes

CRA3689A

CRA3689A AVIC-DRZ90 AVIC-DRZ80 2 3 4 5 66 7 88 9 10 10 10 11 12 13 14 15 1 1 0 OPEN ANGLE REMOTE WIDE SET UP AVIC-DRZ90 SOURCE OFF AV CONTROL MIC 2 16 17 1 2 0 0 1 AVIC-DRZ90 2 3 4 OPEN ANGLE REMOTE SOURCE OFF