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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92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PERFISSION (CONTINUED)<br />
695366 10 Co EV<br />
1Oo 0<br />
MEV<br />
1-oC-ERW IN<br />
JUL<br />
A: ACCURACY 5 PERCENT FOR 100 EV - 10 KEV,<br />
2 PERCENT FOR 10 KEV - 1 MEV<br />
AND 5 PERCENT FOR 1-10 MEVo<br />
O: SPECTRUM INDEXo<br />
STANDARD CROSS <strong>SEC</strong>TIONc<br />
692366 1o 00 MEV<br />
So 00 MEV 3o0X<br />
CoGcCAMPBELL * IN<br />
A: ACCURACY FOR AVERAGE VALUE OF THE ERROR BETWEEN<br />
E AND 2Eo<br />
0: STANDARD FOR PU CROSS-<strong>SEC</strong>TIONSo<br />
FOR FAST REACTORSc<br />
692496 2 00c EV SOOo KEV 2oOX Ho HAEGGBLOM AE<br />
FAST REACTOR CALCULATIONSo<br />
693054 2 5c 3 MV 1 So 0 MEV MoMoISLAM RAM<br />
FOR FAST REACTORSc<br />
214007 So 00 KEV 7o 00 MEV 2o0X MoNjNIKOLAEV FEI<br />
BELOW 20 KEV MEASUREMENTS OF TRANSMISSION CURVES<br />
BY FLAT RESPONSE DETECTOR AND BY SELF DETECTION<br />
METHOD WITH FISSION DETECTOR WANTED FOR<br />
SELFSHIELDING EVALUATIONo<br />
THESE CURVES MUST BE MEA SUREO WITH ATTENUATIONS OF<br />
THE PRIMARY BEAM DOWN TO lo PERCENTo<br />
AVERAGE CS IN FISSION NEUTRON SPECTRUM OF CF-252<br />
TIMES NU-BAR OF CF-252 IS OF- GREAT INTEREST FOR<br />
REDUCING THE DEPENDENCE OF THE ACCURACY OF NEU-<br />
TRON PRODUCTION CALCULATIONS UPON THE ACCURACY<br />
OF THE CF-252 NU-BAR STANDARD (REQUIRED ACCURACY<br />
1 PERCENT >c<br />
ACCURACY DETERMINED BY USE OF THIS CROSS <strong>SEC</strong>TION<br />
AS STANDARD IN FISSION AND CAPTURE MEASUREMENTS<br />
=OR OTHER ISOTOPESc<br />
IF MEASUREMENT IS ABSOLUTE AND PU-239 AND U-238<br />
FISSION CROSS <strong>SEC</strong>TIONS ARE MEASURED RELATIVE TO<br />
U-235 FISSION. THEN 2c 0 PERCENT ACCURACY IS<br />
REQUIREDo<br />
BEST ACCURACY OF lc 5 PERCENT DESIRABLE IN 1o2 TO<br />
2,5 MEV REGION BECAUSE OF U-238 FISSION CROSS<br />
<strong>SEC</strong>TION NORMALIZATION<br />
SEE GENERAL COMMENTS IN THE INTRODUCTION<br />
REQUEST CONSIDERED FULFILLED, WHEN AT LEAST THREE<br />
MEASUREMENTS WITH DIFFERENT METHODS AGREE WITHIN<br />
REQUESTED ACCURACYo<br />
SUBSTANTIAL MODIFICATIONSo<br />
241118 1o 00 MV lo 00 EV NoSTEEN BET<br />
SHAPE ESPECIALLY IMPORTANT AT LOW ENERGYc<br />
NEW REQUEST,<br />
24120 9 4 OOo KEV 2o 00 MEV Wo DAVEY LAS<br />
Q: A RELATIVE MEASUREMENT NORMALIZED TO EXISTING<br />
<strong>DATA</strong> ABOVE 1 MEV IS SUFFICIENT<br />
0: EXTENSION OF LASL ABSOLUTE MEASUREMENT BELOW 1 MEV<br />
TO OVERLAP IMPORTANT LOWER ENERGY <strong>DATA</strong>o<br />
A REFERENCE WHICH IS VITAL TO ALL REACTOR STUDIESo<br />
M: NEW REQUESTc<br />
24202- 1 So 0 MEV AoMICHAUDON<br />
A: ACCURACY 3 PERCENT TO 1 KEV,<br />
o: FOR' CRITICAL ASSEMBLIESc<br />
2 PERCENT ABOVEo<br />
242113<br />
2o 0 X<br />
NEUTRON DOSIMETRY GROUP GEL<br />
0: AVERAGE CROSS <strong>SEC</strong>TION IN A U-235 FISSION SPECTRUM<br />
DESIREDo<br />
O: FOR NORMALIZATION OF AVERAGE CROSS <strong>SEC</strong>TIONS FOR<br />
DOSIMETRY PURPOSES,<br />
252023 lo 00 KEV lOOo KEV<br />
2o OX<br />
HoMATSUNOBU<br />
SAE<br />
o: ABSOLUTE MEASUREMENT WANTEDo<br />
A: ENERGY RESOLUTION - 1 TO 2 PERCENTo<br />
o: EVALUATION OF u-235 <strong>NUCLEAR</strong> <strong>DATA</strong> AND FOR REACTOR<br />
DESIGN CALCULATIONSc<br />
DISCREPANCIES BETWEEN THE EXPERIMENTAL <strong>DATA</strong> ARE<br />
VERY REMARKABLE IN THE ENERGY RANGE BELOW<br />
70 KEVo<br />
M: NEW REOUESTc<br />
252024 1 COo KEV<br />
loOO<br />
MEV<br />
JAP<br />
HoMATSUNOBU<br />
SAE<br />
Q: ABSOLUTE MEASUREMENT WANTEDO<br />
A: ENERGY RESOLUTION - 1 TO 2 PERCENTo<br />
o: EVALUATION OF u-235 <strong>NUCLEAR</strong> <strong>DATA</strong> AND FOR REACTOR<br />
DESIGN CALCULATIONSo<br />
M: NEW REQUESTc<br />
252025 loOO MEV<br />
20o 0<br />
MEV<br />
HoMATSUNOBU<br />
SAE<br />
O: ABSOLUTE MEASUREMENT WANTEOo<br />
A: ACCURACY REQUIRED - 1 TO 2 PERCENTo<br />
ENERGY RESOLUTION - 1 TO 2 PERCENTo<br />
O: EVALUATION OF U-235 <strong>NUCLEAR</strong> <strong>DATA</strong> AND FOR REACTOR<br />
DESIGN CALCULATIONSo<br />
THE EXPERIMENTAL <strong>DATA</strong> ARE COMPARATIVELY POOR IN<br />
THE ENERGY RANGE ABOVE 6 MEV EXCEPT 14 MEV <strong>DATA</strong>o<br />
M: NEW REQUEST,<br />
FISSION LIST PAGE 1 lo 83
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