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