INDC(SEC)-46/U+R+F+SIN DC INTERNATIONAL NUCLEAR DATA ...

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51 ANTIMONY 125 SPONTANEOUS TOTAL GAMMA RAY YIELD Z22fl IS loOX N:SASAMOTO JAE STATUS SGA EDER* - 73 PARIS 1 233. EVALUATION© LRL MEYER* - NP/A 132 177119691© GRE FOIN* - JPR 28 861 (1967)© 0: VIELO PER DISINTEGRATION OF 06c5 AND 10So3 KEV GAMMA RAYS REOUIREDo 0: FOR BURN UP CALCULATION FROM NON-DESTRUCTIVE MEASUREMENTo M: NEW REOUESTc 92 URANIUM 235 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 20X030 SoOO MEV 1Ao 0 MEV SoOX 2 USA Ro Be WALTON LAS 0: DATA DESIRED FOR EXTRAPOLATION TO 15 MEVo CALCULATIONS OF MODERATING ASSEMBLIES FOR U ASSAYo STATUS STATUS A I TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUES, ANL COXo - ANL/NDM-5 (1974).REVIEWo HFA SHALEV* - NSE 51 52(1973). SPECTRUM AVERAGE© I AE MANERO* - REA 10 637( 1972). REVIEWc KFK FIEG - EANCC(E)-157 (1973). WORK IN PROGRESS© FEI TARASKO* - YF 17 1149(1973). IN PROGRESS© SOR AMIEL - 73B0LCGNA.REPo13o TO 15 MEVo LAS KRICK* - .NSE 47 311 (1972)© Oo 1 TO 6© 5 MEVo 92 URANIUM 235 NEUTRON SPECTRUM OF PROMPT GAMMA RAYS EMITTED IN FISSION Z-340QA 25o 3 MV 14o 0 MEV 2 = 0 X 3 CCP S:SoKOVALENKO RI 0: YIELD AND SPECTRA WANTED FOR 5 TO 15 MEV GAMMASo A: 10:0 KEV GAMMA RESOLUTION WANTEDo O: FOR ASSAY OF U IN FUEL ELEMENTS FROM PROMPT GAMMAS, M: NEW REOUESTo 92 URANIUM 235 NEUTRON DELAYED GAMMA SPECTRUM FROM FISSION PRODUCTS Z01029 2 5o3 MV USA Ro Be WALTON LAS a: FISSION PRODUCT GAMMA RAY ENERGIES FROM 0© 25 TO 5 MEVo DELAY TIME FROM 1 MILLISECOND TO 12 HOURS© ASSOCIATE GAMMA RAYS WITH FISSION PRODUCTS IF POSSIBLE© A: GE(LI) RESOLUTION AT lo 2 MEV SHOULD BE 2C S KEV, O: NON-DESTRUCTIVE ASSAY OF U-235© STATUS- LAS LAS ORL BNL HAR WALTON* - PR 17E 1894(19691© FISHER* - PR/B 134 796(1964)© MAIENSCHEIN* - 58 GENEVA VOL©15 366o CHRIEN - HAS DATA FOR U-235 AND PU-239© LARGE* - 69 VIENNA Po637, SOME DATA FOR Uo 92 URANIUM 235 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM 20402i 25o 3 MV So As SKVORTSOV OoAcMILLER KUR KUR O: YIELDS OF ZR—95 AND RU-106 ARE REQUIRED© o: FOR ASSAY OF U IN SPENT FUEL ELEMENTS BY THE FISSION PRODUCT GAMMA RAYSc MI MODIFIED (PARTIALLY FULFILLED)o 222043 HoOKASHITA JAE FISSION YIELD OF RU-106. XE-133, CS-137, CE-141. CE-144. ND—143. ND-144, ND-1AS, ND-146. NO-147, ND-148, AND ND-150o DATA WANTED FOR THERMAL NEUTRONS, FAST REACTOR NEUTRONS(80-800 KEV), FISSION SPECTRUM NEUTRONS AND HIGH ENERGY NEUTRONS(14-15 MEV)© FOR BURN UP CALCULATION FROM DESTRUCTIVE AND NON-DESTRUCTIVE CALCULATIONSo NEW REOUEST© Z22050 50e0X HoOKASHITA JAE FISSION YIELD OF CS-134, PR-142 AND EU-154 WANTEDo OATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR NEUTR0NS(BO-BOO KEV), FISSION SPECTRUM NEUTRONS AND HIGH ENERGY NEUTRONS(14-15 MEV)o FOR BURN UP CALCULATION FROM DESTRUCTIVE AND NON-DESTRUCTIVE CALCULATIONSo NEW REQUESTo SAFEGUARDS LIST PAGE IVo 7
95 AMERICIUM 241 GAMMA FISSICN PRODUCT MASS VI ELD SPECTRUM ( CONTINUED) 722051 HoOKASHITA JAE 0: FISSION YIELD OF SM-152, AND SM-153 WANTEDo DATA WANTED FOR THERMAL NEUTRONS. FAST REACTOR NEUTRONS(80-800 KEV). FISSION SPECTRUM NEUTRONS AND HIGH ENERGY NEUTRONS(1 A-15 ME V)o 0: FOR BURN UP CALCULATION FROM DESTRUCTIVE AND NON-DESTRUCTIVE CALCULATIONSo M: NEW REOUESTo STATUS- K UR MILLER* - SJA 27 281(1568)o -STATUS SRE CCP AE CCP S GA HAR GRE CRC GEV ANL HILLER - KT 12 465(19701 GRECHUSHKINA - TABLES SHOWING THE COMPOSITION OF PROMPT FISSION PRODUCTS FROM U-235, U-238, AND PU—239 FISSICN, ATOM1ZDAT, MOSCOW(1964), FORSYTH* - 70 KARLSRUHE VCLol Po521, G USE V - PROTECTION AGAINST GAMMA RADIATION FROM FISSION PRODUCTS, ATOMIZDAT, MOSCOW( 1 968)c LAMMER* - 73 PARIS PAPER 13, EVALUATION CROUCH - 73 PARIS PAPER 94, EVALUATION, DEVILLERS+ - 73 PARIS PAPER 63, EVALUATION; WALKER - 73 PARIS PAPER 34, EVALUATION, MEEK + - NE00-12154, EVALUATION, GLENDENIN+ - WORK IN PROGRESSo 92 URANIUM 236 NEUTRON CAPTURE CROSS SECTION 722540 1 4o 0 MEV YcNAITO JAE A: ACCURACY REQUIRED AT THERMAL IS 3 PERCENT, 10 PERCENT ABOVE, 0: FOR BURN UP CALCULATION OF A PU LOADED THERMAL REACTOR, M: NEW REQUESTC -STATUS GA GEL S GA HAR SRL CARLSON+ - NP/A 141 577( 1970). DATA THERMAL TO 20 KEVc ROHR+ - EANCCI El-157 ( 1973). IN PROGRESS 5 EV TO 2 KEV.; EDER* - 73 PARIS PAPER 12, COMPILATION, CABELL* - AERE-R-6761(1971), THERMAL, BAUMANN+ - NSE 32 265(19681. 8 PERCENT AT THERMALo 9 2 URANIUM 236 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 701032 3,00 MEV 10,OX Ro Bo WALTON Q: ALSO FOR 14 MEV, NEUTRONS, 0: BACKGROUND CORRECTION IN U- 235 SPENT FUEL ASSAYo 92 URANIUM 236 ENERGY SPECTRUM OF FISSION NEUTRONS 201031 lOoOX USA Rc B;WALTON LAS 0: ONE ENERGY ABOVE FISSION THRESHOLD, 0: BACKGROUND CORRECTIONS IN U-235 SPENT FUEL ASSAYo 92 URANIUM 238 NEUTRON DELAYED NEUTRONS EMITTED PER FISSION 201035 So 00 MEV 14o 0 MEV A Ro Be WALTON LAS o: DATA DESIRED FOR EXTRAPOLATION TO IS MEVo CALCULATIONS OF MODERATING ASSEMBLIES FOR U ASSAYo STATUS A 1 HFA IAE LAS ANL ALD TUTTLEo - NSE 56 37(1975), REVIEW WITH RECOMMENCED VALUESc SHALEV+ - NSE 51 52(1973), FAST REACTOR SPECTRUMc MANERO+ - REA 10 637(1972), REVIEW Ool TO 15 MEV, EVANS* - USNOC-3 127(1972), REVISED DATA AT 3o1 AND IS MEV, COXo ANL/NDM-=(1974)o MEASUREMENT AND EVALUATION, 2 TO 15 MEV, MCTAGGART - EANDC(UK)-151(1973) , FAST REACTOR SPEC MEASUREMENT IN PROGRESS, 92 URANIUM 238 NEUTRON FISSION PRODUCT MASS YIELD SPECTRUM 222.052 1 o 0 X HoOKASHITA JAE FISSION YIELD OF RU-106. XE-133. SM-152, SM-153. CE 141, CE—144. ND-143, ND-144. ND-145, ND-146, NO—147. ND-148, ND-150 AND CS-137 WANTEOo DATA WANTED FOR FISSION SPECTRUM NEUTRONS AND HIGH ENERGY NEUTR0NS(14 - 15 MEVIo FOR BURN UP CALCULATION FROM DESTRUCTIVE AND NON-DESTRUCTIVE MEASUREMENTo NEW REQUESTo SAFEGUARDS LIST PAGE IV o 8
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International Atomic Energy Agency
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- iii - CONTENTS Page I. General In
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I.i I. General Introduction to WREN
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I. iii WRENDA requests for all appl
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I.v I.B. Editorial Policy During co
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I.vii It has been assumed that gene
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H fi22QZfl 15.0 MEV 10.OX 2 FR A.MI
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I.xi Accuracy The fourth field on t
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I.xiii I.D. How to find a request i
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I.XV Table II (page l) QUANTITY SOR
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I. i II. Fission Reactor Developmen
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Il.iii Uncertainty of a point is. s
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I. xxvi The author of the requests
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Il.vii * Priority 2 * Nuclear data
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II.D. LIST OF HITHDRAWN REQUESTS (c
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II.D. LIST OF WITHDRAWN FIECUESTS (
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II.E. Index to Fission Request List
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TARGET 94 PLUTONIUM 241 94 PLUTONIU
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1 HYDROGEN 1 NEUTHCN DIFFERENTIAL E
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3 HYDROGEN 1 NEUTHCN DIFFERENTIAL E
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7 NITS.OGEN 14 NEUTRGN DIFFERENTIAL
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44 HYDROGEN 1 NEUTHCN DIFFERENTIAL
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11 SODIUM 23 RESONANCE PARAMETERS (
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21 SCANDIUM 45 NEUTRCN CAPTURE CROS
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2 3 VANADIUM NEUTRCN INELASTIC_CROS
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£4 CHROMIUM CAPTURE CROSS SECTION
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£5 ~IANGA.NE.SC 55 TOTAL CROSS SEC
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26 I HON NEUTRON ENERGY DIFFERENTIA
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NEUTRCN CAPTURE RESONANCE INTEGRAL
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27 COBALT 55 _ _ NEUTBCN N,ALPHA 21
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TOTAL PHOTON PRODUCTION CROSS SECTI
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28 NICKEL 61 NEUTRCN RESONANCE PARA
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3 1 GALLIUM NEUTRCN N, 2N 742£36 1
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40 ZIRCONIUM 90 NEUTRON ANGULAR DIF
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"0 ZIRCONIUM 93 _ __N|UTKCN CA ? T
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44 R U T H E N I U M 101 NEUTRON CA
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42 MOLYBDENUM 57 NEUTRCN INELASTIC
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45 RHODIUM CAPTURE CROSS SECTION 24
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44 RUTHENIUM 101 NEUTRON CAPTURE CR
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54 XENON 131 NEUTRCN CAPTURE CROSS
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59 PRASEODYMIUM 1 41 RESCNANCE PARA
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61 PROMETHIUM 145 NEUTRCN CAPTURE C
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63 EUROPIUM NEUTRCN DIFFERENTIAL EL
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61 PROMETHIUM 145 NEUTRCN CAPTURE C
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68 ERBIUM 168 NEUTRCN N«ALPHA £55
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72 HAFNIUM 177 NEUTRCN CAPTURE CROS
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7 4 TUNGSTEN 182 NEUTRCN N,ALPHA £
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54 XENON 131 NEUTRCN CAPTURE CROSS
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90 THORIUM 232 NEUTRON ENERGY DIFFE
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91 PROTACTINIUM 233 NEUTRCN CAPTURE
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92 URANIUM 235 NEUTRON DELAYED NEUT
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92 URANIUM 235 NEUTRON ENERGY CIFFc
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92 URANIUM 235 NEUTRONS EMITTED PER
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92 URANIUM 238 NEUTRGN ELASTIC CROS
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92 URANIUM 235 NEUTRON D E L A Y E
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94 PLUTONIUM £38 NEUTRCN FISSION C
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94 PLUTONIUM 239 NEUTRCN N,2N (CONT
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94 PLUTONIUM 239 NEUTRONS EMITTED P
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94 PLUTONIUM 240 NEUTRON INELASTIC
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94 PLUTONIUM 240 NEUTRCN _ NEUTRONS
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94 PLUTONIUM 241 NEUTRON CAPTURE TO
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94 PLUTONIUM 245 NEUTRCN FISSICN CR
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95 AMERICIUM 242 NEUTRCN CAPTURE CR
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Page 140 and 141: 96 CURIUM 244 NEUTRONS EMITTED PER
Page 142: 96 CURIUM 247 NEUTRCN TOTAL CROSS S
Page 145 and 146: 9 8 CAL IFOSMIUM 2EC CAPTURE CROSS
Page 147 and 148: 98 CALIFORNIUM 252 NEUTRCN FISSICN
Page 149 and 150: III. i III. Fusion Reactor Developm
Page 151 and 152: Ill.iii Over the next six months da
Page 153 and 154: JII.V III.C. Priority Criteria .The
Page 155 and 156: Ill.vii III.D. Index to Fusion List
Page 157 and 158: 1 HYDROGEN 2 NEUTRCN N.2N 15Z0S4 1
Page 159 and 160: 3 LITHIUM 6 LITHIUM-6 LITHIUM-6.ALP
Page 161 and 162: 4 BERYLLIUM_9_ __ _ NEUTRCN N.2N _
Page 163 and 164: 9 FLUORINE 19 NEUTRON _ TOTALPHOTON
Page 165 and 166: 23 VANADIUM NEUTRCN ENERGY DIFFEREN
Page 167 and 168: 24 CHROMIUM 52 20o0 MEV 25o OX USA
Page 169 and 170: 28 NICKEL NEUTRCN TOTAL CROSS SECTI
Page 171 and 172: 29 COPPER 63 NEUTRCN CAPTURE CROSS
Page 173 and 174: 41 NIOBIUM 53 NEUTRON DOUBLE DIFFER
Page 175 and 176: 74 TUNGSTEN KEUTRCK N.2N 2S2SM 14o
Page 177 and 178: IV.i IV. Nuclear Safeguards and. Ac
Page 179 and 180: IV.iii Third Priority - (3) Third p
Page 181 and 182: IV. D. DATA REQUEST LIST FOR NUCLEA
Page 183 and 184: 51 ANTIMONY 125 SPONTANEOUS TOTAL G
Page 185 and 186: 51 ANTIMONY 125 SPONTANEOUS TOTAL G
Page 187: 62 SAMARIUM 152 CAPTURE CROSS SECTI
Page 191 and 192: 94 PLUTONIUM 238 SPONTANEOUS NEUTRO
Page 193 and 194: 94PLUT0NIUM 23S NEUTRON p I SSI ON
Page 195 and 196: 94 PLUTONIUM 241 CAPTURE TO FISSION
Page 197 and 198: 95 AMERICIUM 241 GAMMA FISSICN PROD
Page 199 and 200: APPENDICES
Page 201 and 202: LIST OF LABORATORY CODES APPENDIX B
Page 203 and 204: LIST OF LABORATORY CODES APPENDIX B
Page 205 and 206: APPENDIX C page 2 LIST OF JOURNAL R
Page 207 and 208: NAMES AND ADDRESSES OF REQUESTORS A
Page 209 and 210: APPENDIX D page 3 IIJIMA, To JAPAN
Page 211 and 212: APPENDIX D page 5 SCHNEIDER. Vo ALK
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