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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71 LUTETIUM 176 NEUTPCN CAPTURE CROSS <strong>SEC</strong>TION (CONTINUED)<br />
fiaaaat 10o0 EV CoALBERT ROS<br />
STATUS<br />
CROSS <strong>SEC</strong>TION <strong>DATA</strong> NEEDED FOR EVALUATION OF<br />
MEASURED ACTIVATION RATES BY MEANS OF FOILS<br />
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL<br />
NEUTRON FLUXESo<br />
MTR YOUNG - BNL-50276<br />
WUR BRUNNER - PRECISE<br />
B9(1S7C ) .<br />
<strong>DATA</strong><br />
FRCM<br />
THERMAL AVERAGE VALUEo<br />
oOl TO 2 EV TO BE PUBLISHED IN NSEc<br />
71 LUTETIUM 176 NEUTRON N, 2N<br />
652535 1 So 0 MEV lOoOX 3 FR A o MICHAUDON BRC<br />
71 LUTETIUM 176 NEUTRCN CAPTURE RESONANCE INTEGRAL<br />
65.3034 2 So 3 MV 1 Oo 0 KEV Do ALBERT ROS<br />
CROSS <strong>SEC</strong>TION <strong>DATA</strong> NEEDED FOR EVALUATION OF<br />
MEASURED ACTIVATION RATES BY MEANS OF FOILS<br />
(ESPECIALLY SPECTRAL INDICES) FOR THERMAL<br />
NEUTRON FLUXESo<br />
653035 lo 00 EV VoCHRISTOV BAC<br />
FOR ACTIVATION DETECTORS FOR THERMAL NEUTRON FLUX<br />
OETERMI NATIONo<br />
72 HAFNIUM DIFFERENTIAL ELASTIC CROSS <strong>SEC</strong>TION<br />
661536<br />
ISoO MEV lOoOX USA NoSTEEN BET<br />
ACCURACY IN AVERAGE (1-COS) 10 PERCENTo<br />
ENERGY RESOLUTION - 10 PERCENTo<br />
WANTED FOR THERMAL REACTOR DESIGNo<br />
SUBSTANTIAL MODIFICATIONSo<br />
STA TUS-<br />
AE<br />
ANL<br />
HOLMQVIST+ - AE 430 (197C)o<br />
SHERWOOD* - NSE 39 67(1969), <strong>DATA</strong> TO loS MEVo<br />
72 HAFNIUM CAPTURE CROSS <strong>SEC</strong>TION<br />
621524 loOO MV loOO EV 2o OX NoSTEEN<br />
Ro EHRLICH<br />
BET<br />
KAP<br />
NEEDED FOR MONTE CARLO CALCULATIONS OF BURNUP IN<br />
THERMAL REACTORSo<br />
72 HAFNIUM NEUTRON NEUTRON EMISSION CROSS <strong>SEC</strong>TION<br />
661532 loOO EV 1 So 0 MEV ISoOX NoSTEEN BET<br />
0: <strong>SEC</strong>ONDARY ENERGY DISTRIBUTION REOUIREOo<br />
A: INCIDENT AND EXIT ENERGY RESOLUTIONS IS PERCENTo<br />
o: FOR DESIGN OF THERMAL REACTORS HAVING APPRECIABLE<br />
QUANTITIES OF HFo<br />
M: SUBSTANTIAL MODIFICATIONSO<br />
72 HAFNIUM 174 NEUTRON CAPTURE CROSS <strong>SEC</strong>TION<br />
661536 1o 00 MV So 00 KEV Ro EHRLICH KAP<br />
THERMAL VALUE WANTED TO 20 PERCENTo<br />
NEED AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo<br />
BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTURE<br />
WIDTHS NEEDED WITH 10 PERCENT ACCURACYo<br />
ABOVE 100 EV. 20 PERCENT ACCURACY REQUIREDo<br />
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo<br />
72 HAFNIUM 1 76 CAPTURE CROSS <strong>SEC</strong>TION<br />
621526 lo 00 MV So 00 KEV NoSTEEN<br />
RoEHRLICH<br />
BET<br />
KAP<br />
THERMAL VALUE WANTED TO 20 PERCENTo<br />
BELOW 1 EV, 40 PERCENT ACCURACY NEEDEDo<br />
BETWEEN 10 AND 100 EV, TOTAL. NEUTRON AND CAPTUF<br />
WIDTHS NEEDED WITH 10.PERCENT ACCURACYo<br />
ABOVE 100 EV. 20 PERCENT ACCURACY REQUIREDo<br />
AVERAGE P-WAVE CAPTURE WIDTH TO 20 PERCENTo<br />
S-WAVE STRENGTH FUNCTION TO 40 PERCENTo<br />
TO RESOLVE DISCREPANCIES IN RESONANCE INTEGRALo<br />
NEEDED FOR MONTE CARLO BURN UP CALCULATIONSo<br />
SUBSTANTIAL MODIFICATIONSo<br />
232056 1Oo 0 MV So 00 KEV lOoOX<br />
FR HoTELLIER SAC<br />
O: REACTOR CALCULATIONSo<br />
STATUS<br />
SAC RIBONo - 72B0LCGNA 1 235. PEVIEWo<br />
FISSION LIST PAGE IIo 54
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