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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TOTAL PHOTON PRODUCTION CROSS <strong>SEC</strong>TION (CONTINUED)<br />
692X2S lo 00 KEV 1 So 0 MEV 1Oo OX 2 FR CoCEVILLERS SAC<br />
0: GAMMA SPECTRA REQUIRED,<br />
A: ENERGY RESOLUTION OF 250 KEV FOR GAMMA RAYS LESS<br />
THAN 1 MEV AND SCO KEV FOR ENERGIES GREATER<br />
THAN 1 MEVo<br />
O: FOR FAST REACTOR SHIELDING CALCULATIONSo<br />
EVALUATION MAY BE SUFFIC IENTc<br />
Z2XH52 2 So 3 MV 1 Oo C MEV 20 o OX 2 USA PcBcHEMMIG AEC<br />
O: <strong>SEC</strong>ONDARY ENERGY DISTRIBUTION REQUIRED,<br />
o: FOR SHIELDING AND GAMMA HEATING CALCULATIONSo<br />
STATUS<br />
STATUS<br />
ORL CICKENSo - ORNL-TM-4379. <strong>DATA</strong> 1 TC 2C MEVo<br />
28 NICKEL NEUTRON NEUTRON EMISSION CROSS <strong>SEC</strong>TION<br />
6i2X23 2o GC KEV 1 So 0 MEV Co DEVILLERS SAC<br />
Q: <strong>SEC</strong>ONDARY ENERGY DISTRIBUTION FEQUIREDc<br />
A: RESOLUTION FOR PRIMARY AND <strong>SEC</strong>ONDARY NEUTRONS<br />
10 PERCENT,<br />
o: FOR FAST REACTOR SHIELDING CALCULATIONSo<br />
EVALUATION MAY BE SUFFICIENTo<br />
28 NICKEL N, F<br />
Z02010 15o 0 MEV lOoOX FR JoYo EARRE CAD<br />
0: FOR FAST REACTOR CALCULATIONS,<br />
28 NICKEL<br />
£S2X32 1 5o 0 MEV 20o OX CcOEVILLERS<br />
o: FOR FAST REACTOR CALCULATIONSc<br />
EVALUATION MAY BE SUFFICIENTo<br />
Z21051 1 Oc 0 MEV 1 5oOX A B,HUTCH INS GEB<br />
O: TO DETERMINE HE PRODUCTION IN FAST REACTORSo<br />
Z223Sa 1 5c 0 MEV 1 FR JoY,BARRE CAD<br />
o: FOR FAST REACTOR CALCULATIONSo<br />
2 8 NICKEL NEUTRCN<br />
CAPTURE RESONANCE INTEGRAL<br />
6SH0S 0,50 EV USA RcEHRLICH KAP<br />
O: REMOVE OR CORRECT FOR N.P CONTRI BUT IONc<br />
28 NICKEL 56<br />
652X33 1 5o 0 MEV Ac MICHAUDON 8RC<br />
0: PRODUCTION OF N1-57 (36,4 HOUR),<br />
O: ACTIVATION DETECTOR,<br />
EVALUATION MAY BE SUFFICIENTo<br />
DISAGREEMENT BETWEEN JERONYMOC SACLAY) AND OTHERS,<br />
28 NICKEL 56 NEUTRCN<br />
Z2XOSS 1 5o 0 MEV USA<br />
0: FOR USE AS FAST FLUENCE MONITORc<br />
SUBSTANTIAL MOD 1FICATION So<br />
Z321U NEUTRON DOSIMETRY GROUP GEL<br />
O: AVERAGE CROSS <strong>SEC</strong>TION IN A U-235 FISSION SPECTRUM<br />
DESIREDc<br />
o: FOR NORMALIZATION OF AVERAGE CROSS <strong>SEC</strong>TIONS FOR<br />
DOSIMETRY PURPOSES,<br />
ZA2XX1 2o 10 MEV 7o 00 MEV 5oOX 1 EUR NEUTRON DOSIMETRY GROUP GEL<br />
0: ROUTINE FAST NEUTRON FLUENCE MONITORo<br />
STRONG DISCREPANCY BETWEEN DIFFERENTIAL <strong>DATA</strong> AND<br />
AVERAGE VALUE IN U-235 FISSION NEUTRON SPECTRUMc<br />
STATUS<br />
STATUS<br />
IRK WAGNER* - APA 37 288(1973). <strong>DATA</strong> 2 TO 20 MEVo<br />
GEL PAULSEN* - EAN<strong>DC</strong>(E)-150 (1972), MEASUREMENT IN PROGRESSo<br />
N <strong>DC</strong> SCHETT+ - EANCC-95 ( 1974), COMPILATION OF EXPERIMENTAL <strong>DATA</strong> AVAILABLE AS OF JANUARY 1974,<br />
ANL SMITH* - ANL/NDM-10 (1975). MEASUREMENTS AND EVALUATION FROM Oc4 TO 10 MEVc<br />
FISSION LIST PAGE IIo 25