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

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92 URANIUM 238 NEUTRGN ELASTIC CROSS SECTION 742061 loOC KEV 15o 0 MEV SoOX FR AoMICHAUDON BRC O: FOR CRITICAL ASSEMBLIESo 92 URANIUM 238 DIFFERENTIAL ELASTIC CROSS SECTION 651407 1o OC KEV 1 Co 0 MEV CoEoTILL Eo HUT CH IN S Po BeHEMMIG AoMcPERRY ANL GEB AEC ORL ACCURACY 10 PERCENT FROM 1 TO 3C0 KEVo 5 PERCENT FROM 300 KEV TO 2 MEVo 10 PERCENT FROM 2 TO 10 MEVo FACTORS OF 2 LOWER ACCURACY WOULD BE USEFUL ON SHORT TERMo 242062 1=00 KEV 1 So 0 MEV SoOX 2 FR AoMICHAUDON BRC 0: FOR CRITICAL ASSEMBLlESc STATUS -STATUS GEL KNITTER* - ZP 244 358( 1570 1 , DATA lc 5 TO 5oS MEVo ANL SMITH* - LSNDC-11 25(1974)o RESULTS TO 4 MEVo ABD BUCHER+ - USNDC-11 25(1974). DATA 7 TO 14 MEVc SMALL-ANGLE SCATTERINGc GEL KNITTER* - EANCC(E)-1 5 0 (1972). WCRK CONTINUESo 92 URANIUM 238 NEUTRON INELASTIC CROSS SECTION 652262 15o 0 MEV JoYcEARRE CAD 0: ALTERNATE QUANTITY - NONELASTIC CROSS SECTIONo 0: FOR FAST REACTOR CALCULATIONSc 6S236S 8 0o 0 KEV SOOo KEV C HoHAEGGBLOM AE A: ACCURACY REQUIRED TO BETTER THAN 10 PERCENTo 0: NEEDED FOR FAST REACTOR CALCULATIONSo 6S2333 1 o 20 ME V 2o 00 MEV lOoOX R FoWELLER KFK O: LEVEL EXCITATION CROSS SECTIONS FOR THE 45 AND 148 KEV LEVELS WANTEDo 242063 1 5o 0 MEV Sc OX AcMICHAUOON BRC 01 FOR CRITtCAL ASSEMBLIES, 254021 1 OOo KEV 1 Oo 0 MEV LoNcUSACHEV FE I FROM OO1-0C 8 MEV ACCURACY 4o0 PERCENT, PRIORITY 2 ACCURACY 3o4 PERCENTo FROM 0o8-lo 4 MEV ACCURACY 4o 0 PERCENT, PRIORITY 2 ACCURACY 2o7 PERCENTc FROM 1o4-2c 5 MEV ACCURACY 5o 0 PERCENT, PRIORITY 2 ACCURACY 3=C PERCENTo FROM 2c 5-So C MEV ACCURACY 12 PERCENT. PRIORITY 2 ACCURACY 10 PERCENTc FROM 5O0-6O5 MEV ACCURACY 7o 8 PERCENT, PRIORITY 2 ACCURACY 7c 0 PERCENTo FROM 6o 5-1C MEV ACCURACY 10 PERCENT, PRIORITY 2 ACCURACY 10 PERCENTc NEED FOR FAST REACTOR CALCULATIONo FOR MORE DETAIL SEE INTRODUCTIONo NEW REOUESTc 92 URANIUM 238 NEUTRON ANGULAR DIFFERENTIAL INELASTIC CROSS SECTION 652350 2o CO MEV lOoOX 2 GER FoWELLER KFK 92 URANIUM 238 NEUTRCN ENERGY DIFFERENTIAL INELASTIC CROSS SECTION 65127C SOoO KEV 10c 0 MEV SoOX Co EcTILL Be HUTCHINS PoBcHEMMIG ANL GEB AEC 0: EMISSION INSTEAD OF INELASTIC AND N.2N MIGHT BE USEFULo A: ACCURACY OF 20 PERCENT WOULD BE USEFULo ENERGY RESOLUTION 5 PERCENTo M: SUBSTANTIAL MODIFICATIONSo 652331 1 So 0 MEV JoY,BARRE CAD 0: SEPARATION OF LEVELS UP TO 2 MEV REQUIREDo A: ACCURACY ON NUCLEAR TEMPERATURE ABOVE 2 MEVo o: FOR FAST REACTOR CALCULATIONSo 632,334 7o 00 MEV 14o 0 MEV SoOX FISSION LIST PAGE IIo 77
92 URANIUM 235 NEUTRON DELAYED N E U T R O N S EMITTED PERFISSION (CONTINUED) Z14015 SOOO KEV 15o 0 MEV McN o NIKOLAEV FEI DECISION ABOUT TOTAL INELASTIC CROSS SECTION AT 1 = 0 TO 2o 5 MEV WANTEDc TEMPERATURE FOR INELASTIC NEUTRONS WANTED AT THE HIGHER ENERGIESc SPECTRA AND CROSS SECTION FOR DIRECT INELASTIC SCATTERING PROCESSES TO BE INVESTIGATED IN THE MEV REGION AS WELL AS DIRECT MECHANISM CONTRIB- UTlONSo CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION THRESHOLD OF U-238 WANTED TO lo5 - 2o 0 PERCENTo CROSS SECTION FOR INELASTIC REMOVAL BELOW FISSION THRESHOLD OF PU-240 OR NP-237 WANTED TO 3 - 5 PERCENT: EXCITATION CS FOR FIRST LEVEL ABOVE THRESHOLD TO 2 MEV SHOULD BE MEASURED WITH 5 PERCENT ACCURACYo NEUTRON SPECTRA TO BE MEASURED WITH 5 PERCENT ACCURACY AT 2=515 MEVo SEE GENERAL COMMENTS IN THE INTRODUCTIONo PRECISION MEASUREMENTS OF MENTIONED INTEGRAL PARAMETERS IN SHELL TRANSMISSION EXPERIMENTS WITH CF-252 NEUTRON SOURCE AND U-238 AND NP-237 FISSION THRESHOLD DETECTORS AS WELL AS BY NEUTRON SPECTROMETER SEEMS VERY USEFULo SUBSTANTIAL MOO IF ICAT.I ONSo -STATUS GEL PEL HAR GEL ANL KFK AE L T I KNITTER* - ZP 244 358( 1971). DATA 1c 5 TO 2o3 MEVo BARNARD* - 70 HELSINKI 2 103. DATA TC lc4 MEVo ARMITAGE* - AERE-PR/NP18 (1972). IN PROGRESS lo1 TO 2=4 MEVc KNITTER* - EANCC(E)—15G (1972), WCfiK CCNTINUESo SMITH* - LSNOC-11 25(1974)o NEW RESULTS TO 4 MEVo VOSS* - EANDC(E ) -157 (1973), IN PROGRESS TC 2 MEVo CONDE+ - WORK IN PROGRESSo MARCELLA* - DATA 1 TO 2o 7 MEVo 92 URANIUM 238 NEUTRON DOUBLE DIFFERENTIAL INELASTIC CROSS SECTION £52252 1o 00 MEV 2o 50 MEV UK CcGoCAMPBELL WIN o: FOR FAST REACTORSc 65,3062 3 09o KEV 1 Oo 0 MEV lOoOX 1 BAN MoMc ISLAM RAM 0: FOR FAST REACTORSc Z420S4 1 5o 0 MEV SoOX FR AoMICHAUDON STA TUS- STATUS- -STATUS HAR ARM ITAGEo - IN FROGRESSo 92 URANIUM 238 NEUTRON NCN-ELASTIC CROSS SECTION 65.2.0 £1 ICOo KEV 1Oo 0 MEV lOoOX BAN M0M0ISLAM RAM O: FOR FAST REACTORSo Z1401Z 1 1 Co 0 KEV 1 5o 0 MEV MoNcNIKOLAEV FEI DIRECT MEASUREMENTS BY SHELL TRANSMISSION DESIRABLE WITH 3-5 PERCENT ACCURACY, FOR EVALUATION OF INELASTIC SCATTERING CROSS SECTION FOR FAST REACTORSo 92 URANIUM 238 NEUTRCN CAPTURE CROSS SECTION 651415 SCO, EV 1Oo 0 MEV C0E0TILL Be HUTC H INS P o BeHEMMIG ANL GEB AEC ACCURACY 6 PERCENT FROM 500 EV TO 1 KEV, 4 PERCENT FROM 1 KEV TO 300 KEV, 6 PERCENT FROM 300 KEV TO 500 KEV, 10 PERCENT FROM 500 KEV TO 10 MEVo ACCURACY OF 10 PERCENT FROM 1 KEV TO 10 MEV, USEFULc HIGHEST PRIORITY NEED FOR FAST REACTOR CALCULATIONSo 651435 10,0 KEV 1 Oo 0 MEV COECTILL BoHUTCHINS PoBeHEMMIG Ao.M,PERRY ANL GEB AEC ORL NEEDED IS RATIO OF CAPTURE CROSS SECTION U-238 TO FISSION CROSS SECTION OF PU-239 OR U-235o DIRECT RATIO NEEDED TO SUPPLEMENT SEPARATE MEASUREMENT, ACCURACY 1,5 PERCENT BELOW 300 KEV, 7 PERCENT ABOVEo INTERMEDIATE ACCURACY USEFUL NEAR TERMo 652401 SoOO MV 60 00 EV J0G0TYROR A: ACCURACY REQUIRED o03 BARNSo 0: FOR THERMAL REACTORSo £52402 4,00 EV 500, EV 2,OX HOTELLIER SAC 0: RELATIVE TO SIGMA(N.G) AT THERMALo O: FOR CALCULATION OF IEFFo EVALUATION MAY SUFFICE IF IT EXPLAINS DISCREPANCIES, FISSION LIST PAGE 1 lo 83
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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
Page 64 and 65: 28 NICKEL 61 NEUTRCN RESONANCE PARA
Page 66 and 67: 3 1 GALLIUM NEUTRCN N, 2N 742£36 1
Page 68 and 69: 40 ZIRCONIUM 90 NEUTRON ANGULAR DIF
Page 70 and 71: "0 ZIRCONIUM 93 _ __N|UTKCN CA ? T
Page 72 and 73: 44 R U T H E N I U M 101 NEUTRON CA
Page 74 and 75: 42 MOLYBDENUM 57 NEUTRCN INELASTIC
Page 76 and 77: 45 RHODIUM CAPTURE CROSS SECTION 24
Page 78 and 79: 44 RUTHENIUM 101 NEUTRON CAPTURE CR
Page 80 and 81: 54 XENON 131 NEUTRCN CAPTURE CROSS
Page 82 and 83: 59 PRASEODYMIUM 1 41 RESCNANCE PARA
Page 84 and 85: 61 PROMETHIUM 145 NEUTRCN CAPTURE C
Page 86 and 87: 63 EUROPIUM NEUTRCN DIFFERENTIAL EL
Page 88 and 89: 61 PROMETHIUM 145 NEUTRCN CAPTURE C
Page 90 and 91: 68 ERBIUM 168 NEUTRCN N«ALPHA £55
Page 92 and 93: 72 HAFNIUM 177 NEUTRCN CAPTURE CROS
Page 94 and 95: 7 4 TUNGSTEN 182 NEUTRCN N,ALPHA £
Page 96 and 97: 54 XENON 131 NEUTRCN CAPTURE CROSS
Page 98 and 99: 90 THORIUM 232 NEUTRON ENERGY DIFFE
Page 100 and 101: 91 PROTACTINIUM 233 NEUTRCN CAPTURE
Page 102 and 103: 92 URANIUM 235 NEUTRON DELAYED NEUT
Page 106 and 107: 92 URANIUM 235 NEUTRON ENERGY CIFFc
Page 110 and 111: 92 URANIUM 235 NEUTRONS EMITTED PER
Page 116 and 117: 92 URANIUM 235 NEUTRON D E L A Y E
Page 122 and 123: 94 PLUTONIUM £38 NEUTRCN FISSION C
Page 124 and 125: 94 PLUTONIUM 239 NEUTRCN N,2N (CONT
Page 126 and 127: 94 PLUTONIUM 239 NEUTRONS EMITTED P
Page 128 and 129: 94 PLUTONIUM 240 NEUTRON INELASTIC
Page 130 and 131: 94 PLUTONIUM 240 NEUTRCN _ NEUTRONS
Page 132 and 133: 94 PLUTONIUM 241 NEUTRON CAPTURE TO
Page 134 and 135: 94 PLUTONIUM 245 NEUTRCN FISSICN CR
Page 136 and 137: 95 AMERICIUM 242 NEUTRCN CAPTURE CR
Page 138 and 139: 95 AMERICIUM 242 NEUTRCN CAPTURE CR
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
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23 VANADIUM NEUTRCN ENERGY DIFFEREN
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24 CHROMIUM 52 20o0 MEV 25o OX USA
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28 NICKEL NEUTRCN TOTAL CROSS SECTI
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29 COPPER 63 NEUTRCN CAPTURE CROSS
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41 NIOBIUM 53 NEUTRON DOUBLE DIFFER
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74 TUNGSTEN KEUTRCK N.2N 2S2SM 14o
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IV.i IV. Nuclear Safeguards and. Ac
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IV.iii Third Priority - (3) Third p
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IV. D. DATA REQUEST LIST FOR NUCLEA
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51 ANTIMONY 125 SPONTANEOUS TOTAL G
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51 ANTIMONY 125 SPONTANEOUS TOTAL G
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62 SAMARIUM 152 CAPTURE CROSS SECTI
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95 AMERICIUM 241 GAMMA FISSICN PROD
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94 PLUTONIUM 238 SPONTANEOUS NEUTRO
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94PLUT0NIUM 23S NEUTRON p I SSI ON
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94 PLUTONIUM 241 CAPTURE TO FISSION
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95 AMERICIUM 241 GAMMA FISSICN PROD
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APPENDICES
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LIST OF LABORATORY CODES APPENDIX B
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LIST OF LABORATORY CODES APPENDIX B
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APPENDIX C page 2 LIST OF JOURNAL R
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NAMES AND ADDRESSES OF REQUESTORS A
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APPENDIX D page 3 IIJIMA, To JAPAN
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APPENDIX D page 5 SCHNEIDER. Vo ALK
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