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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96 CURIUM 243 NEUTRON CAPTURE CROSS <strong>SEC</strong>TION (CONTINUED)<br />
1SZ0A3 2 Oo 0 EV lOoO MEV Po YUMOTO<br />
hoMATSUNOBU<br />
PNC<br />
SAE<br />
A." ACCURACY REQUIRED 10 TO 20 PERCENTo<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 />
JUL IHLE* - JIN 34(E) 2427(1972). PILEo<br />
JAP o(1975), NO EXPERIMENTAL <strong>DATA</strong> ABOVE 26 EVo<br />
96 CURIUM 243 NEUTRON FISSICN CROSS <strong>SEC</strong>TION<br />
2S20A2 1 Oo 0 M V 1o 00 EV lOoOX<br />
Ro YUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
0: ENERGY DEPENDENCE WANTEDo<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 REQUESTc<br />
Z52DA4<br />
2 Oo 0 E V<br />
1 OOo<br />
lOoOX<br />
RoYUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
o: 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 />
2S20A5<br />
3o 00<br />
MEV<br />
1Oo 0<br />
MEV<br />
RcYUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
A: ACCURACY REQUIRED 10 TO 20 PERCENTo<br />
O: 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 REQUESTc<br />
STATUS-<br />
JUL IHLE* - JIN 34(C) 2427(1972), PILEo<br />
LRL BROWNE* - NCSAC-42 135(1971), MEASUREMENT THERMAL TO<br />
LAS FULLWOOD* - LA-4420 (1970), CATA Ooll TO 2o9 MEVo<br />
LRL HULET* - PR 107 1294(1957). THERMALo<br />
JAP o(1975) , NO EXPERIMENTAL <strong>DATA</strong> FROM 26 EV TC 106KEV<br />
JAP o(1975) , NC EXPERIMENTAL <strong>DATA</strong> ABOVE 3 MEV o<br />
96 CURIUM 244 NEUTRCN CAPTURE CROSS <strong>SEC</strong>TION<br />
62X1*2 1 Oo 0 KEV 1Oo 0 MEV BohUTCHINS GEB<br />
A: ACCURACY OF 5 TO 10 PERCENT IN Rio<br />
0: FOR SPENT FUEL SHIELDINGo<br />
TO EVALUATE CF PRODUCTIONo<br />
M: SUBSTANTIAL MODIFICATIONSO<br />
I321QS 5o 00 KEV lOoOX FR HoTELLIER<br />
O: BURN UP PHYSIC So<br />
Z520AS SOOo EV 1 Oo 0 MEV<br />
RoYUMOTO<br />
HoMATSUNOBU<br />
PNC<br />
SAE<br />
A: ACCURACY REQUIRED 10 TO 20 PERCENTc<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 REQUESTc<br />
STATUS<br />
LAS MOORE* - PR/C 3 1656(1971), <strong>DATA</strong> 20 EV TO 10 KEVo<br />
-STATUS<br />
96 CURIUM 244 NEUTRON FISSION CROSS <strong>SEC</strong>TION<br />
222X0 S SOOo EV ISoO MEV JoYo EARRE CAD<br />
O: VALUE RELATIVE TO U-235 FISSION CROSS <strong>SEC</strong>T I ONo<br />
0: FOR FAST REACTOR CALCULATIONSo<br />
Z52fl»fl 1 o 00 KEV lOoO KEV RoYUMOTO<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 />
-STATUS<br />
LAS MOORE* - PF/C 3 1656(1971). <strong>DATA</strong> 20EV TO 3 MEVo<br />
SRL BENJAMIN* - NSE 47 203(1972). THERMAL CROSS <strong>SEC</strong>TION AND RESONANCE INTEGRAL RELATIVE TO U-235<br />
FISSION LIST PACE lie 102
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