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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95 AMERICIUM 241<br />
GAMMA<br />
FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED)<br />
722051 HoOKASHITA JAE<br />
0: FISSION YIELD OF SM-152, AND SM-153 WANTEDo<br />
<strong>DATA</strong> WANTED FOR THERMAL NEUTRONS. FAST REACTOR<br />
NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS<br />
AND HIGH ENERGY NEUTRONS(1 A-15 ME V)o<br />
0: FOR BURN UP CALCULATION FROM DESTRUCTIVE AND<br />
NON-DESTRUCTIVE CALCULATIONSo<br />
M: NEW REOUESTo<br />
STATUS-<br />
K UR<br />
MILLER* - SJA 27 281(1568)o<br />
-STATUS<br />
SRE<br />
CCP<br />
AE<br />
CCP<br />
S GA<br />
HAR<br />
GRE<br />
CRC<br />
GEV<br />
ANL<br />
HILLER - KT 12 <strong>46</strong>5(19701<br />
GRECHUSHKINA - TABLES SHOWING THE COMPOSITION OF PROMPT FISSION PRODUCTS FROM U-235, U-238, AND<br />
PU—239 FISSICN, ATOM1ZDAT, MOSCOW(1964),<br />
FORSYTH* - 70 KARLSRUHE VCLol Po521,<br />
G USE V - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS, ATOMIZDAT, MOSCOW( 1 968)c<br />
LAMMER* - 73 PARIS PAPER 13, EVALUATION<br />
CROUCH - 73 PARIS PAPER 94, EVALUATION,<br />
DEVILLERS+ - 73 PARIS PAPER 63, EVALUATION;<br />
WALKER - 73 PARIS PAPER 34, EVALUATION,<br />
MEEK + - NE00-12154, EVALUATION,<br />
GLENDENIN+ - WORK IN PROGRESSo<br />
92 URANIUM 236 NEUTRON CAPTURE CROSS <strong>SEC</strong>TION<br />
722540<br />
1 4o 0 MEV YcNAITO JAE<br />
A: ACCURACY REQUIRED AT THERMAL IS 3 PERCENT, 10<br />
PERCENT ABOVE,<br />
0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL<br />
REACTOR,<br />
M: NEW REQUESTC<br />
-STATUS<br />
GA<br />
GEL<br />
S GA<br />
HAR<br />
SRL<br />
CARLSON+ - NP/A 141 577( 1970). <strong>DATA</strong> THERMAL TO 20 KEVc<br />
ROHR+ - EANCCI El-157 ( 1973). IN PROGRESS 5 EV TO 2 KEV.;<br />
EDER* - 73 PARIS PAPER 12, COMPILATION,<br />
CABELL* - AERE-R-6761(1971), THERMAL,<br />
BAUMANN+ - NSE 32 265(19681. 8 PERCENT AT THERMALo<br />
9 2 URANIUM 236 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION<br />
701032 3,00 MEV 10,OX Ro Bo WALTON<br />
Q: ALSO FOR 14 MEV, NEUTRONS,<br />
0: BACKGROUND CORRECTION IN U- 235 SPENT FUEL ASSAYo<br />
92 URANIUM 236 ENERGY SPECTRUM OF FISSION NEUTRONS<br />
201031 lOoOX USA Rc B;WALTON LAS<br />
0: ONE ENERGY ABOVE FISSION THRESHOLD,<br />
0: BACKGROUND CORRECTIONS IN U-235 SPENT FUEL ASSAYo<br />
92 URANIUM 238 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION<br />
201035 So 00 MEV 14o 0 MEV<br />
A Ro Be WALTON LAS<br />
o: <strong>DATA</strong> DESIRED FOR EXTRAPOLATION TO IS MEVo<br />
CALCULATIONS OF MODERATING ASSEMBLIES FOR U ASSAYo<br />
STATUS<br />
A 1<br />
HFA<br />
IAE<br />
LAS<br />
ANL<br />
ALD<br />
TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUESc<br />
SHALEV+ - NSE 51 52(1973), FAST REACTOR SPECTRUMc<br />
MANERO+ - REA 10 637(1972), REVIEW Ool TO 15 MEV,<br />
EVANS* - USNOC-3 127(1972), REVISED <strong>DATA</strong> AT 3o1 AND IS MEV,<br />
COXo ANL/NDM-=(1974)o MEASUREMENT AND EVALUATION, 2 TO 15 MEV,<br />
MCTAGGART - EAN<strong>DC</strong>(UK)-151(1973) , FAST REACTOR SPEC MEASUREMENT IN PROGRESS,<br />
92 URANIUM 238 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM<br />
222.052 1 o 0 X HoOKASHITA JAE<br />
FISSION YIELD OF RU-106. XE-133. SM-152, SM-153.<br />
CE 141, CE—144. ND-143, ND-144. ND-145, ND-1<strong>46</strong>,<br />
NO—147. ND-148, ND-150 AND CS-137 WANTEOo<br />
<strong>DATA</strong> WANTED FOR FISSION SPECTRUM NEUTRONS AND<br />
HIGH ENERGY NEUTR0NS(14 - 15 MEVIo<br />
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND<br />
NON-DESTRUCTIVE MEASUREMENTo<br />
NEW REQUESTo<br />
SAFEGUARDS LIST PAGE IV o 8
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