ENTRY 33101 20170307 31783310100000001 SUBENT 33101001 20170307 31783310100100001 BIB 12 24 3310100100002 TITLE Measurements of fission product yield in the 3310100100003 neutron-induced fission of 238U with average energies 3310100100004 of 9.35 MeV and 12.52 MeV 3310100100005 AUTHOR (S.Mukerji, P.D.Krishnani, B.S.Shivashankar, V.K.Mulik,3310100100006 S.V.Suryanarayana, H.Naik, A.Goswami) 3310100100007 INSTITUTE (3INDTRM,3INDMNP,3INDPOO) 3310100100008 REFERENCE (J,KPS,65,18,2014) 3310100100009 FACILITY (VDGT,3INDTRM) 14UD Pelletron accelerator 3310100100010 SAMPLE Natural 238U metal foil wrapped with 0.025 mm thick 3310100100011 super pure aluminum foil of purity 99.99%. The size 3310100100012 of 238U metal foil was 1.0 cm2 with thickness of 3310100100013 634.2 mg/cm2 3310100100014 INC-SOURCE (P-LI7) Natural lithium with a thickness of 4.0 3310100100015 mg/cm2 sandwiched between two tantalum foils. The 3310100100016 front and back tantalum foil were of thickness 3.4 3310100100017 mg/cm2 and 0.025-mm-thick respectively. 3310100100018 DETECTOR (HPGE) 80 cc HPGe detector coupled to PC based 4K 3310100100019 channel analyser. The resolution was 1.8 keV FWHM at 3310100100020 1332.5 keV of 60Co. 3310100100021 METHOD (ACTIV) Irrad./Cool. = 10h/1h for 16 MeV 3310100100022 Irrad./Cool. = 5h/1h for 20 MeV 3310100100023 MONITOR (92-U-238(N,F)40-ZR-97,(CUM),FY) 3310100100024 MONIT-REF (,S.Daroczy+,S,IAEA-169,(3),281,1974) 3310100100025 HISTORY (20170307C) Compiled by Theodore Selwyn.G, MCC, INDIA 3310100100026 ENDBIB 24 0 3310100100027 NOCOMMON 0 0 3310100100028 ENDSUBENT 27 0 3310100199999 SUBENT 33101002 20170307 31783310100200001 BIB 4 23 3310100200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA) 3310100200003 DECAY-DATA ((1.)38-SR-91,9.63HR,DG,1024.3,0.33) 3310100200004 ((2.)38-SR-92,2.71HR,DG,1384.9,0.90) 3310100200005 ((3.)40-ZR-95,64.02D,DG,756.7,0.54) 3310100200006 ((4.)40-ZR-97,16.91HR,DG,743.4,0.93) 3310100200007 ((5.)44-RU-105,4.44HR,DG,724.4,0.47) 3310100200008 ((6.)48-CD-115-G,53.46HR,DG,336.2,0.459) 3310100200009 ((7.)51-SB-129-G,4.32HR,DG,812.4,0.43) 3310100200010 ((8.)52-TE-132,3.2D,DG,228.1,0.88) 3310100200011 ((9.)53-I-133-G,20.8HR,DG,529.9,0.87) 3310100200012 ((10.)56-BA-139,83.03MIN,DG,165.8,0.237) 3310100200013 ((11.)58-CE-143,33.03HR,DG,293.3,0.428) 3310100200014 ((12.)60-ND-147,10.98D,DG,91.1,0.28) 3310100200015 ERR-ANALYS (ERR-T) Total uncertainty (7-11%) 3310100200016 (ERR-S,5.,10.) Statistical error 3310100200017 (ERR-SYS) Total systematic error (~4.7%) 3310100200018 (ERR-1) Uncertainty in neutron flux estimate (~3%) 3310100200019 (ERR-2) Uncertainty due to irradiation time (~0.5%) 3310100200020 (ERR-3) Uncertainty due to detector efficiency 3310100200021 calibration (~3%) 3310100200022 (ERR-4) Uncertainty due to half life of fission 3310100200023 products and gamma ray abundances(~2%) 3310100200024 STATUS (TABLE) Table 1 and 2 of J,KPS,65(2014)18 3310100200025 ENDBIB 23 0 3310100200026 COMMON 5 3 3310100200027 ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 3310100200028 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3310100200029 4.7 3. 0.5 3. 2. 3310100200030 ENDCOMMON 3 0 3310100200031 DATA 6 24 3310100200032 EN ELEMENT MASS DATA ERR-T DECAY-FLAG 3310100200033 MEV NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3310100200034 9.35 38. 91. 3.831 0.211 1.3310100200035 9.35 38. 92. 3.976 0.412 2.3310100200036 9.35 40. 95. 4.687 0.121 3.3310100200037 9.35 40. 97. 5.206 0.412 4.3310100200038 9.35 44. 105. 3.346 0.302 5.3310100200039 9.35 48. 115. 0.541 0.051 6.3310100200040 9.35 51. 129. 1.441 0.151 7.3310100200041 9.35 52. 132. 5.184 0.402 8.3310100200042 9.35 53. 133. 5.301 0.401 9.3310100200043 9.35 56. 139. 4.511 0.405 10.3310100200044 9.35 58. 143. 3.306 0.351 11.3310100200045 9.35 60. 147. 2.209 0.101 12.3310100200046 12.52 38. 91. 3.560 0.151 1.3310100200047 12.52 38. 92. 3.705 0.351 2.3310100200048 12.52 40. 95. 4.950 0.122 3.3310100200049 12.52 40. 97. 5.206 0.412 4.3310100200050 12.52 44. 105. 3.520 0.404 5.3310100200051 12.52 48. 115. 1.061 0.301 6.3310100200052 12.52 51. 129. 1.491 0.205 7.3310100200053 12.52 52. 132. 4.501 0.404 8.3310100200054 12.52 53. 133. 5.051 0.405 9.3310100200055 12.52 56. 139. 4.706 0.406 10.3310100200056 12.52 58. 143. 3.110 0.361 11.3310100200057 12.52 60. 147. 2.393 0.110 12.3310100200058 ENDDATA 26 0 3310100200059 ENDSUBENT 58 0 3310100299999 ENDENTRY 2 0 3310199999999