ENTRY 10839 20150513 14071083900000001 SUBENT 10839001 20150513 14071083900100001 BIB 12 31 1083900100002 TITLE Neutron absorption cross sections of radioactive 1083900100003 nuclides. 1083900100004 AUTHOR (R.Rundberg) 1083900100005 REFERENCE (T,RUNDBERG,1978) 1083900100006 INSTITUTE (1USABLN) 1083900100007 FACILITY (REAC,1USABNL) High flux beam reactor 1083900100008 DETECTOR (GELI) Coaxial GeLi detector with 40 cubic cm active 1083900100009 volume. Absolute efficiency determined with Co-60 and 1083900100010 Nb-94 standard NBS point sources. 1083900100011 INC-SPECT Thermal distribution of thermal neutrons assumed to 1083900100012 be a Maxwell-Boltzmann distribution. Westcott 1083900100013 convention used to obtain 2200 m/sec cross section 1083900100014 and resonance integral from data obtained with 1083900100015 cadmium-wrapped samples. 1083900100016 METHOD (ACTIV) Runs made with and without cadmium in sample 1083900100017 holder. Standard counting geometry obtained with use 1083900100018 of two foot lucite tower mounted over detector with 1083900100019 pre-set distance slots. 1083900100020 MONITOR 1(27-CO-59(N,G)27-CO-60,,SIG,,MXW) 1083900100021 2(79-AU-198(N,G)79-AU-199,,SIG,,MXW) 1083900100022 3(71-LU-176(N,G)71-LU-177,,SIG,,MXW) Fast flux 1083900100023 determined relative to Ni-58(n,proton)Co-58 reaction) 1083900100024 DECAY-MON 1(27-CO-60-M,10.4MIN,DG,133.25) 1083900100025 2(79-AU-199,3.14D,DG,158.375,,DG,208.201) 1083900100026 3(71-LU-177-G,6.7D,DG,208.36,,DG,112.95) 1083900100027 DECAY-DATA Values taken by compiler from chart of the nuclides 1083900100028 HISTORY (19790212C) 1083900100029 (19800219A) BIB correction. 1083900100030 (20150513A) BP: Updated to new date formats, lower 1083900100031 case. Corrections according last EXFOR rules and 1083900100032 Dict. Subentry five reaction string correction. 1083900100033 ENDBIB 31 0 1083900100034 COMMON 1 3 1083900100035 EN-DUMMY 1083900100036 EV 1083900100037 0.0253 1083900100038 ENDCOMMON 3 0 1083900100039 ENDSUBENT 38 0 1083900199999 SUBENT 10839002 20150513 14071083900200001 BIB 5 7 1083900200002 REACTION (58-CE-138(N,G)58-CE-139,,SIG,,MXW) 1083900200003 ANALYSIS Indirect determination of maximum cross section based 1083900200004 on Cd ratio. Data reflects lower limit of measurement 1083900200005 technique. 1083900200006 DECAY-DATA (58-CE-139-G,137.5D,DG,166.) 1083900200007 STATUS (TABLE) page 76. 1083900200008 HISTORY (19800219A) BIB correction. 1083900200009 ENDBIB 7 0 1083900200010 NOCOMMON 0 0 1083900200011 DATA 1 1 1083900200012 DATA-MAX 1083900200013 B 1083900200014 500. 1083900200015 ENDDATA 3 0 1083900200016 ENDSUBENT 15 0 1083900299999 SUBENT 10839003 20150513 14071083900300001 BIB 6 7 1083900300002 REACTION (39-Y-89(N,2N)39-Y-88,,SIG,,MXW) 1083900300003 DECAY-DATA (39-Y-88,106.6D,DG,1836.1,,DG,898.0) 1083900300004 SAMPLE Chemically pure oxide: 99.9999-Percent purity Y(2)O(3).1083900300005 COMMENT Cross section too small to produce significant 1083900300006 activation, value given is assumed. 1083900300007 STATUS (TABLE) page 76. 1083900300008 HISTORY (19800219A) BIB correction. 1083900300009 ENDBIB 7 0 1083900300010 NOCOMMON 0 0 1083900300011 DATA 1 1 1083900300012 DATA-MAX 1083900300013 MB 1083900300014 1. 1083900300015 ENDDATA 3 0 1083900300016 ENDSUBENT 15 0 1083900399999 SUBENT 10839004 20150513 14071083900400001 BIB 5 5 1083900400002 REACTION (75-RE-185(N,2N)75-RE-184,,SIG,,MXW) 1083900400003 DECAY-DATA (75-RE-184-G,38.D,DG,903.3,,DG,792.1) 1083900400004 SAMPLE 99.95-percent pure rhenium powder 1083900400005 STATUS (TABLE) page 82. 1083900400006 HISTORY (19800219A) BIB correction. 1083900400007 ENDBIB 5 0 1083900400008 NOCOMMON 0 0 1083900400009 DATA 1 1 1083900400010 DATA 1083900400011 B 1083900400012 8940. 1083900400013 ENDDATA 3 0 1083900400014 ENDSUBENT 13 0 1083900499999 SUBENT 10839005 20150513 14071083900500001 BIB 6 11 1083900500002 REACTION (75-RE-184(N,G)75-RE-185,,SIG,,MXW) 1083900500003 INC-SPECT Neutron temperature is -26 degrees centigrade 1083900500004 METHOD The method used destruction by neutron absorption, 1083900500005 allows to observe large cross sections. The measured 1083900500006 value was the absorption cross section of radioactive 1083900500007 Re-184, presumably Re-184(n,g)Re-185. 1083900500008 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 1083900500009 STATUS (TABLE) page 83. 1083900500010 HISTORY (19800219A) BIB correction. 1083900500011 (20150513A) BP: Reaction string correction per author 1083900500012 comment. 1083900500013 ENDBIB 11 0 1083900500014 NOCOMMON 0 0 1083900500015 DATA 2 1 1083900500016 DATA-MIN DATA-ERR 1083900500017 B B 1083900500018 1470. 140. 1083900500019 ENDDATA 3 0 1083900500020 ENDSUBENT 19 0 1083900599999 SUBENT 10839006 20150513 14071083900600001 BIB 4 4 1083900600002 REACTION (25-MN-55(N,2N)25-MN-54,,SIG,,MXW) 1083900600003 DECAY-DATA (25-MN-54,312.5D,DG,865.) 1083900600004 SAMPLE 99.999-Percent pure MnO(2) 1083900600005 STATUS (TABLE) page 86. 1083900600006 ENDBIB 4 0 1083900600007 NOCOMMON 0 0 1083900600008 DATA 1 1 1083900600009 DATA-MIN 1083900600010 B 1083900600011 1000. 1083900600012 ENDDATA 3 0 1083900600013 ENDSUBENT 12 0 1083900699999 SUBENT 10839007 20150513 14071083900700001 BIB 4 5 1083900700002 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG,,MXW) 1083900700003 DECAY-DATA (40-ZR-95,59.5D,DG,723.9) Values of half-life and 1083900700004 gamma energy from author. 1083900700005 SAMPLE Sample used in the form of ZrO(2) 1083900700006 STATUS (TABLE) page 87. 1083900700007 ENDBIB 5 0 1083900700008 NOCOMMON 0 0 1083900700009 DATA 1 1 1083900700010 DATA 1083900700011 MB 1083900700012 52. 1083900700013 ENDDATA 3 0 1083900700014 ENDSUBENT 13 0 1083900799999 ENDENTRY 7 0 1083999999999