ENTRY 30926 20141212 31673092600000001 SUBENT 30926001 20141212 31673092600100001 BIB 14 42 3092600100002 TITLE Investigation of thermal-neutron capture gamma-rays on 3092600100003 Ni-58(n,g)Ni-59 3092600100004 AUTHOR (A.W.Carbonari,B.R.Peceqvilo) 3092600100005 INSTITUTE (3BZLIPE) 3092600100006 REFERENCE (C,88MITO,,133,198806) 3092600100007 (R,IEA-78,1978)the basic features of the internal 3092600100008 target facility are described in more 3092600100009 details. 3092600100010 SAMPLE A well mixed sample of natural nickel and melamine 3092600100011 (C3-H6-N6) contained within a reactor grade graphite 3092600100012 capsule. 3092600100013 FACILITY (REAC,3BZLIPE) 3092600100014 INC-SOURCE (REAC) the neutron flux was about 5.2x10**11 n/sec/cm 3092600100015 METHOD (MOMIX) 3092600100016 The gamma-ray spectrum of thermal neutron capture on 3092600100017 58Ni was measured in the energy range of 3.7 To 9.3MeV 3092600100018 The experiment was carried out at the tangential 3092600100019 reactor channel. The gamma-rays were detected by Ge(Li)3092600100020 -NaI(Tl) pair spectrometer. The partial cross sections 3092600100021 for several gamma-ray transitions have been calculated 3092600100022 and by summing all of them,was determined the total 3092600100023 thermal neutron capture cross section for 58-Ni(n,g). 3092600100024 INC-SPECT Thermal neutron spectrum. 3092600100025 DETECTOR (BPAIR).-Ge(Li)and NaI(Tl) pair spectrometer consisting3092600100026 of a 45.5 Cc true coaxial Ge(Li) detector which 3092600100027 fits into a cylindrical opening in the common 3092600100028 housing of 2 optically separated(5x6)inc. 3092600100029 Nai(Tl) crystals.- 3092600100030 CORRECTION The determination of the efficiency curve as a function3092600100031 the gamma-ray energies was made experimentally, by 3092600100032 measuring a set of gamma-rays with very well-known 3092600100033 energy and intensity values. For this purpose was used 3092600100034 gamma-rays from 14-N(n,g)N-15 and 35-Cl(n,g)Cl-36 3092600100035 reactions in the region of 1.8 To 11 MeV. 3092600100036 ERR-ANALYS No error analysis given. 3092600100037 STATUS data given from C,88mito,Ca09,88.Tab.1 3092600100038 HISTORY (19880912C) VOF 3092600100039 (19940316A) HW.- Reaction code corrected in subent 004.3092600100040 (20070810A) ref. corrected 3092600100041 (20070821A) BIB section updated. ref. on conference was3092600100042 corrected (page number added) 3092600100043 (20121212U) VS. BIB minor corrections. 3092600100044 ENDBIB 42 0 3092600100045 COMMON 1 3 3092600100046 EN-DUMMY 3092600100047 EV 3092600100048 0.0253 3092600100049 ENDCOMMON 3 0 3092600100050 ENDSUBENT 49 0 3092600199999 SUBENT 30926002 20070821 31243092600200001 BIB 1 2 3092600200002 REACTION (28-NI-58(N,G)28-NI-59,,SPC) 3092600200003 Gamma lines measured in the range 3700 keV to 9300 keV.3092600200004 ENDBIB 2 0 3092600200005 NOCOMMON 0 0 3092600200006 DATA 3 11 3092600200007 E DATA E-LVL-FIN 3092600200008 KEV PC/INC KEV 3092600200009 4031.35 0.53 4968.00 3092600200010 4977.18 0.30 4035.00 3092600200011 5817.08 3.54 3181.81 3092600200012 5972.84 0.92 3025.70 3092600200013 6105.13 2.35 2893.80 3092600200014 6383.65 2.63 2414.91 3092600200015 7263.56 0.33 1734.78 3092600200016 7697.43 1.33 1301.52 3092600200017 8121.09 4.56 878.09 3092600200018 8534.21 25.14 465.06 3092600200019 8999.18 52.71 0.00 3092600200020 ENDDATA 13 0 3092600200021 ENDSUBENT 20 0 3092600299999 SUBENT 30926003 20070821 31243092600300001 BIB 4 12 3092600300002 REACTION (28-NI-58(N,G)28-NI-59,PAR,SIG) 3092600300003 MONITOR (7-N-14(N,G)7-N-15,,SIG) 3092600300004 was used the 5297,5592,7298 and 8310 keV gamma-ray 3092600300005 transitions from 14-N(n,g) reaction as standards in 3092600300006 order to evaluate the partial cross section of the 3092600300007 primary g-rays of the 58-Ni(n,g) reaction. 3092600300008 MONIT-REF (12718001,M.A.ISLAM+,J,NIM,188,243,1981)the monitor dat3092600300009 given as a average sigma data from exfor 12718.002 and 3092600300010 12718.003 3092600300011 ANALYSIS The area of the double escape peak of the measured 3092600300012 gamma-rays was obtained by a gaussian fitting in the 3092600300013 computer code. 3092600300014 ENDBIB 12 0 3092600300015 COMMON 1 3 3092600300016 MONIT 3092600300017 MB 3092600300018 77.2 3092600300019 ENDCOMMON 3 0 3092600300020 DATA 3 11 3092600300021 E DATA DATA-ERR 3092600300022 KEV B B 3092600300023 4031.35 0.005 0.001 3092600300024 4977.18 0.014 0.001 3092600300025 5817.08 0.160 0.003 3092600300026 5972.84 0.041 0.001 3092600300027 6105.13 0.106 0.002 3092600300028 6583.65 0.119 0.002 3092600300029 7263.56 0.015 0.001 3092600300030 7697.43 0.060 0.001 3092600300031 8121.09 0.206 0.004 3092600300032 8534.21 1.136 0.022 3092600300033 8999.18 2.381 0.045 3092600300034 ENDDATA 13 0 3092600300035 ENDSUBENT 34 0 3092600399999 SUBENT 30926004 20070821 31243092600400001 BIB 5 6 3092600400002 REACTION (28-NI-58(N,G)28-NI-59,,SIG) 3092600400003 MONITOR (7-N-14(N,G)7-N-15,,SIG) 3092600400004 ANALYSIS The total cross section was calculated by summing all 3092600400005 the partial cross section given in subentry 003 3092600400006 STATUS (DEP,30926003) 3092600400007 HISTORY (19940316A) HW.- Reaction code corrected.- 3092600400008 ENDBIB 6 0 3092600400009 COMMON 1 3 3092600400010 MONIT 3092600400011 MB 3092600400012 77.2 3092600400013 ENDCOMMON 3 0 3092600400014 DATA 2 1 3092600400015 DATA DATA-ERR 3092600400016 B B 3092600400017 4.52 0.10 3092600400018 ENDDATA 3 0 3092600400019 ENDSUBENT 18 0 3092600499999 ENDENTRY 4 0 3092699999999