INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...
INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...
INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...
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97 BERKELIUM 249 NEUTRON CAPTURE CROSS <strong>SEC</strong>TION<br />
631-254 LOCO KEV FoJoMC CROSSON SRL<br />
0: SHAPE OF THERMAL CROSS <strong>SEC</strong>TION ESPECIALLY<br />
IMPORTANTo<br />
A: 10 PERCENT THERMAL AND RESONANCE INTEGRALo<br />
O: FOR CF PRODUCTIONO<br />
M: SUBSTANTIAL MODIFICATIONS,<br />
252624 2 So 3 MV 1 Oo 0 MEV 20o0X 1 JAP RoYUMOTO PNC<br />
HoMATSUNOBU<br />
SAE<br />
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
M: NEW REQUESTO<br />
STATUS<br />
STATUS<br />
ANL MAGNUSSON* PR 9( 1576(1954), PILEo<br />
SRL FOLGER+ - 68WASH 1279, THERMALo<br />
97 BERKELIUM 249 NEUTRCN FISSICN CROSS <strong>SEC</strong>TION<br />
752672<br />
2 5o 3 MV<br />
200o<br />
2 0 o 0 X<br />
Ro YUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
NEW REQUESTc<br />
752672<br />
5o 00<br />
MEV<br />
1Oo 0<br />
MEV<br />
20 oO X<br />
Rc YUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
NEW REQUESTc<br />
KUR VOROTNIKOV* - NF/A ISO 56(1970), <strong>DATA</strong> 0o6 TO 4oC MEVo<br />
SRL RUSCHEo - ANS 14 344(1571), THERMALo<br />
CCP FORMUSHKIN+ - YF 14 73( 1971 >. <strong>DATA</strong> lo 5 TO 15 MEVo<br />
LRL BROWNE* - NCSAC-42 135(1971), MEASUREMENT FLANNEDo<br />
97 BERKELIUM 250 NEUTRCN CAPTURE CROSS <strong>SEC</strong>TION<br />
252626 2So3 MV lOoO MEV 20o0X 2 JAP RcYUMOTO PNC<br />
HoMATSUNOBU<br />
SAE<br />
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
M: NEW REQUESTo<br />
STATUS<br />
STATUS<br />
JAP o(1975), NC EXPERIMENTAL <strong>DATA</strong> IN THE ENERGY RANGE FROM THERMAL TO 10 MEVo<br />
97 BERKEL IUM 250 NEUTRON FISSICN CROSS <strong>SEC</strong>TION<br />
252525 25o3 MV 1Oo 0 MEV 20 o OX 2 JAP RoYUMOTO PNC<br />
HoMATSUNOBU<br />
SAE<br />
0: REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
M: NEW REQUESTo<br />
STATUS<br />
STATUS<br />
ANL DIAMOND* - JIN 30 2553(1968), THERMALo<br />
98 CALIFORNIUM 249 NEUTRCN CAPTURE CROSS <strong>SEC</strong>TION<br />
252522 lOoO MEV RcYUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
A:<br />
o:<br />
ACCURACY REQUIRED 10 TO 20 PERCENTo<br />
REACTOR BURN-UP CALCULATIONS AND ESTIMATION OF<br />
TRANS-URANIUM NUCLIDE BUILD-UP IN SPENT FUELo<br />
NEUTRON SHIELDING OF SPENT-FUEL TRANSPORT CASKo<br />
NEW REQUESTo<br />
STATUS<br />
BRK HARVEY* - PR «S 581(1954), FILEo<br />
ORL HALPERIN* - 0RNL-47Q6 4711971 I. THERMALo<br />
98 CALIFORNIUM 2S0 NEUTRON TOTAL CROSS <strong>SEC</strong>TION<br />
621132 25o3 MV 1Oo 0 KEV 20o'0X USA FoJoMC CROSSON SRL<br />
BS=s9BSBasaa*Bsaaae<br />
j: RESONANCE ENERGIES DESIREDo<br />
A: NEED 20 PERCENT ACCURACY IN RESONANCE INTEGRALo<br />
O: TO EVALUATE CF PRODUCTIONo<br />
FISSION LIST PAGE I Io 107
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