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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94 PLUTONIUM 241 CAPTURE TO FISSION RATIO (ALPHA)<br />
222047<br />
14o 0 MEV YCNAITO JAE<br />
A: ACCURACY REQUIRED AT THERMAL IS 1 PERCENT. 5<br />
PERCENT ABOVEc<br />
O: FOR BURN UP CALCULATION OF A PU LOADED THERMAL<br />
REACTOR,<br />
M: NEW REQUESTO<br />
ORL WESTON+ - LSN<strong>DC</strong>-7 179(1973), IN PROGRESS THERMAL TO 200 KEVo<br />
-STATUS<br />
ANL OAVEY - 70HELSINKI 2 119o REVIEW , Ocl TO 10 MEV,<br />
KAP EI LAND* - NSE 44 180(1971), PILE SPECTRUM,<br />
94 PLUTONIUM 241 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION<br />
2010<strong>46</strong><br />
14c 0 MEV lOcOX Ro Be WALTON LAS<br />
<strong>DATA</strong> DESIRED FOR EXTRAPOLATION TO IS MEVo<br />
CALCULATIONS OF MODERATING ASSEMBLIES FOR<br />
ASSAYo<br />
STATUS-<br />
STATUS-<br />
A I TUTTLEo - NSE S6 37(1975), REVIEW WITH RECOMMENCED VALUES,<br />
LAS KEEPIN - NUC 2C 150( 1962), CNLY AT THERMALo<br />
ANL . MEADOWSo (1974 lo WORK BEING PLANNEDc<br />
-STATUS<br />
94 PLUTONIUM 241 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM<br />
204021<br />
ScAcSKVORTSOV<br />
OoA,MILLER<br />
KUR<br />
KUR<br />
Q: YIELD OF RU-144 WANTEDo<br />
o: FOR ASSAY OF PU IN FUEL ELEMENTS BY MEANS<br />
3F FISSION PRODUCT GAMMA RADIATIONo<br />
M: SUBSTANTIAL MODIFICATION SO<br />
Z22052<br />
HoOKASHITA<br />
JAE<br />
FISSION YIELO OF CS-137 AND CE-144 WANTED:<br />
<strong>DATA</strong> WANTED FOR THERMAL NEUTRONS. FAST REACTOR<br />
NEUT RON S(80-80C KEV). FISSION SPECTRUM NEUTRONS<br />
AND HIGH ENERGY NEUTRONS(14—15 MEV)o<br />
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND<br />
NON-DESTRUCTIVE CALCULATIONSo .<br />
NEW REQUESTo<br />
722056 1 o 0 X HcOKASHITA JAE<br />
FISSION YIELD OF XE-133, CE-141, ND-143. NO-144,<br />
ND-145, ND-1<strong>46</strong>. ND-147, ND-148. ND-150, SM-152,<br />
SM-153 AND RU-106 WANTEOo<br />
<strong>DATA</strong> WANTED FOR THERMAL NEUTRONS, FAST REACTOR<br />
NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS<br />
AND HIGH ENERGY NEUTRONS(14-15 MEV)0<br />
FOR BURN UP CALCULATION FROM DESTRUCTIVE AND<br />
NON-DESTRUCTIVE CALCULATIONSo<br />
NEW REQUEST,<br />
222059 SOo OX 2 JAP HoOKASHITA JAE<br />
0: FISSION YIELD OF CS-134, PR-142, AND EU-154<br />
WANTED,<br />
<strong>DATA</strong> WANTED FOR THERMAL NEUTRONS. FAST REACTOR<br />
NEUTRONS(80-800 KEV), FISSION SPECTRUM NEUTRONS<br />
AND HIGH ENERGY NEUTRONS( 1 4-1 5 MEV)o<br />
o: FOR BURN UP CALCULATION FROM DESTRUCTIVE AND<br />
NON-DESTRUCTIVE CALCULATIONSo<br />
M: NEW REQUEST,<br />
STATUS<br />
STATUS<br />
HAR CROUCH - 73 PARIS PAPER 94, THERMAL EVALUATION<br />
CRC WALKER - 73 PARIS PAPER 34, THERMAL EVALUATION<br />
GEV MEEK* - NEDO-12154, THERMAL EVALUATIONo<br />
94 PLUTONIUM 241 MISC<br />
202023 VoSCHNEIDER ALK<br />
STATUS<br />
DRF GETTING - PR 168 1388. MEASUREMENT TO 5o0 PERCENT,<br />
o:<br />
SPECIFIC DECAY HEAT IN WATTS/GRAM REQUIREDo<br />
PERCENTAGE OF HEAT CARRIED OFF BY LONG RANGE<br />
PARTICLES (X-RAYS,GAMMA RAYS) USEFULo<br />
FOR CALORIMETRIC PU DETERMINATION,<br />
94 PLUTONIUM 242 FISSICN HALF LIFE<br />
241153 loOX 2 USA NoSc BEYER ANL<br />
A: ACCURACY 3-5 PERCENT USEFUL IN SHORT TERMo<br />
O: FOR CALCULATION OF THE EFFECTIVE PU-240 FOR<br />
SPONTANEOUS FISSION MEASUREMENTS OF PU IN<br />
<strong>NUCLEAR</strong> MATERIALS SAFEGUARDSo.<br />
M: NEW REQUESTo<br />
SAFEGUARDS LIST PAGE IVo 14