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INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...

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95 AMER ICIUM 243 NEUTRON CAPTURE CROSS <strong>SEC</strong>TION (CONTINUED!<br />

74-1126 1 c GO KEV 200o KEV Po Bo HEMMIG<br />

o: FOR SPENT FUEL SHI ELDINGo<br />

M: NEW REQUESTO<br />

762636 1 Oo 0 MEV<br />

RoYUMOTO<br />

HoMATSUNOBU<br />

PNC<br />

SAE<br />

Q: PRODUCTION OF AM-244 AND AM-244 M WANTEOo<br />

A: ACCURACY REQUIRED 5 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 REQUEST;<br />

STA TUS-<br />

ANC<br />

JUL<br />

MTR<br />

BUC<br />

SIMPSON* - ANCP-1060 (19721. <strong>DATA</strong> c5 EV TO 1 KEVo<br />

IHLE* - JIN 34(61 2427(19721. PILEo<br />

BERRETH+ - IN-14C7 66(1970). RESONANCE PARAMETERS TO 25 EVo<br />

BOCA+ - NF/A 134 541(1569), <strong>DATA</strong> 0o3 TO 4 MEVo<br />

95 AMERICIUM 243 NEUTRON FISSION CROSS <strong>SEC</strong>TION<br />

712111 15o 0 MEV JoYo EARRE<br />

0: RELATIVE TO U-235 FISSIONo<br />

0: FOR FAST REACTOR CALCULATIONSo<br />

75233-7 1 Oo 0 MEV<br />

RoYUMOTO<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 />

STA TUS<br />

J<br />

CCP FORMLSHKIN + - YF 5 966(1967), VALUE AT 15 MEVo<br />

DUB NAD 1 * - JINR-P7-5162(1970), 16 MEVo<br />

LAS SEEGERc - LA-442C (1970). CATA 49 EV TO 3 MEVo<br />

95 AMERICIUM 243 NEUTRON NEUTRONS EMITTED PER FISSION (NU BAR)<br />

712.112 500; EV ISoO MEV Jo Yc BARRE<br />

0: RELATIVE TO CF-2S2 NUc<br />

0: FOR FAST REACTOR CALCULATIONSo<br />

95 AMERICIUM 243 NEUTRCN ABSORPTION RESONANCE INTEGRAL<br />

712.114 1 Oo OX 2 FR HoTELLIER SAC<br />

95 AMERICIUM 244 NEUTRCN CAPTURE CROSS <strong>SEC</strong>TION<br />

25204C 25o 3 MV 1 Oo 0 MEV 2 JAP RoYUMOTO PNC<br />

HoMATSUNOBU<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 />

95 AMERICIUM 244 NEUTRON FISSICN CROSS <strong>SEC</strong>TION<br />

75263S 2 5o 3 MV 1Oo 0 MEV 2 JAP Ro YUMOTO PNC<br />

HoMATSUNOBU<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 REQUESTC<br />

STATUS " STATUS<br />

LAS HUBLETo - HASh-1033 28(1961). THERMALo<br />

ANL VANDENBOSCH* - JIN 23 187(1962). THERMALo<br />

96 CURIUM 242 NEUTRCN CAPTURE CROSS <strong>SEC</strong>TION<br />

6-7113S 2 5o 3 MV<br />

F o Jo MC<br />

CROSSON<br />

o: TARGET HALF-LIFE 163 Do<br />

o: FOR PU-238 PRODUCTIONO<br />

712116 ICoO KEV lo 00 MEV lOoOX<br />

C: FOR CALCULATIONS OF SPONTANEOUS FISSION IN FAST<br />

REACTORSo<br />

Z32107 1 Oo 0 MV 5o 00 KEV lOoOX FR HoTELLIER SAC<br />

•: BURN UP PHYSICSo<br />

FISSION LIST PAGE Ho 100

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