ENTRY 21722 20230211 2172200000001 SUBENT 21722001 20230211 20231011 2172200100001 BIB 15 62 2172200100002 TITLE Inelastic scattering of 14 MeV neutrons by medium 2172200100003 weight nuclei 2172200100004 AUTHOR (I.Fujita,M.Sonoda,A.Katase,Y.Wakuta,H.Tawara, 2172200100005 M.Hyakutake,K.Iwatani) 2172200100006 REFERENCE (J,NST,9,301,1972) 2172200100007 INSTITUTE (2JPNKYU) For I.F,M.S,A.K,Y.W,H.T,M.H,. 2172200100008 FACILITY (CCW,2JPNKYU) Cockroft-Walton accelerator. 2172200100009 INC-SOURCE (D-T) 200 keV deuterons on tritium target. 2172200100010 SAMPLE Scatterers were placed 76.1 mm from the tritium target2172200100011 and were of natural elements in a light aluminium 2172200100012 can, 30 mm diameter, 30 mm thick. Chemical purities 2172200100013 were as follows: 2172200100014 Ti - 99.5%, V - 99.8%, Cr - 99.0%, 2172200100015 Mn - 99.0%, Fe - 99.99%, Co - 99.9%, 2172200100016 Ni - 99.5%, Cu - 99.999%, Zn 85%, 2172200100017 Ge - 99.9999999%, As - 99.98% 2172200100018 METHOD (TOF,ASSOP,PSD) Associated particle technique for 2172200100019 measurement of the energy spectra of inelastically 2172200100020 scattered neutrons at 110 degrees. Flight path 1 m. 2172200100021 Start pulses from alpha detector and stop from 2172200100022 neutron detector. 2172200100023 DETECTOR (SCIN) Neutron detector was NE213 liquid scintillator 2172200100024 diameter 127 mm, 50 mm thick, with pulse shape 2172200100025 discrimination against gammas. Counting efficiency 2172200100026 determined by neutron scattered from hydrogen at 2172200100027 various angles. 2172200100028 Alpha detector was a 0.05 mm thick plastic 2172200100029 scintillator placed 50 mm from the tritium target. 2172200100030 ANALYSIS Level densities are derived from measured inelastic 2172200100031 neutron spectra with a compound nucleus - statistical 2172200100032 model theory. A Fermi gas model, assuming a constant 2172200100033 nuclear temperature was used. 2172200100034 A high energy limit of 6.5 MeV was set to avoid the 2172200100035 contribution from the tail of elastically scattered 2172200100036 neutrons. 2172200100037 A lower energy limit was set for each element, 2172200100038 somewhat higher than the largest energy of neutrons 2172200100039 emitted in (n,2n) reactions. The effect of (n,pn) 2172200100040 and (n,2n) reactions on isotopes of low abundance 2172200100041 was neglected. 2172200100042 For the inverse reaction cross section three different2172200100043 sets were used. See flags. 2172200100044 MONITOR (6-C-12(N,EL)6-C-12,,DA) Absolute efficiency was 2172200100045 calibrated using the cross section of neutron elastic 2172200100046 scattering on carbon at 30 and 40 degrees, with 2172200100047 values taken from NP,53,177,1964. 2172200100048 MONIT-REF (11286003,R.L.Clarke+,J,NP,53,177,1964) 2172200100049 CORRECTION .Background corrections were made with an empty 2172200100050 aluminium sample can. 2172200100051 ERR-ANALYS (DATA-ERR) Uncertainties are standard deviations from a2172200100052 least squares fit to the experimental data. For the 2172200100053 differential elastic cross sections the overall 2172200100054 relative uncertainty is estimated to be about 8% 2172200100055 HISTORY (19810113C) 2172200100056 (19840106U) A.P.T. Japan code changed to JPN 2172200100057 (20030730A) date is corrected. REACTION codes changed 2172200100058 (20030801U) energy moved to subentries 2172200100059 (20110227A) SD:Updated to new date formats,lower case. 2172200100060 corrected according to last EXFOR rules and Dict. 2172200100061 REACTION code in Subents 024-034 corrected. 2172200100062 (20170120U) SD: Year of publ. corrected (1973 -> 1972).2172200100063 (20230211A) SD: Correction in Subents 038, 045. 2172200100064 ENDBIB 62 0 2172200100065 NOCOMMON 0 0 2172200100066 ENDSUBENT 65 0 2172200199999 SUBENT 21722002 20110227 22262172200200001 BIB 4 9 2172200200002 REACTION 1(22-TI-0(0,0),,TEM) Nuclear temperature. 2172200200003 2(22-TI-0(0,0),,TEM) Nuclear temperature. 2172200200004 3(22-TI-0(0,0),,TEM) Nuclear temperature. 2172200200005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200200006 2. Bjoklund-Fernbach potential. 2172200200007 3. Cross section assumed constant. 2172200200008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200200009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200200010 (20030801U) last checking has been done. 2172200200011 ENDBIB 9 0 2172200200012 NOCOMMON 0 0 2172200200013 DATA 6 1 2172200200014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200200015 MEV MEV MEV MEV MEV MEV 2172200200016 1.05 1.E-02 1.18 2.E-02 1.21 2.E-022172200200017 ENDDATA 3 0 2172200200018 ENDSUBENT 17 0 2172200299999 SUBENT 21722003 20110227 22262172200300001 BIB 4 9 2172200300002 REACTION 1(23-V-51(0,0),,TEM) Nuclear temperature. 2172200300003 2(23-V-51(0,0),,TEM) Nuclear temperature. 2172200300004 3(23-V-51(0,0),,TEM) Nuclear temperature. 2172200300005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200300006 2. Bjoklund-Fernbach potential. 2172200300007 3. Cross section assumed constant. 2172200300008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200300009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200300010 (20030801U) last checking has been done. 2172200300011 ENDBIB 9 0 2172200300012 NOCOMMON 0 0 2172200300013 DATA 6 1 2172200300014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200300015 MEV MEV MEV MEV MEV MEV 2172200300016 1.23 2.E-02 1.23 3.E-02 1.13 2.E-022172200300017 ENDDATA 3 0 2172200300018 ENDSUBENT 17 0 2172200399999 SUBENT 21722004 20110227 22262172200400001 BIB 4 9 2172200400002 REACTION 1(24-CR-0(0,0),,TEM) Nuclear temperature. 2172200400003 2(24-CR-0(0,0),,TEM) Nuclear temperature. 2172200400004 3(24-CR-0(0,0),,TEM) Nuclear temperature. 2172200400005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200400006 2. Bjoklund-Fernbach potential. 2172200400007 3. Cross section assumed constant. 2172200400008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200400009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200400010 (20030801U) last checking has been done. 2172200400011 ENDBIB 9 0 2172200400012 NOCOMMON 0 0 2172200400013 DATA 6 1 2172200400014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200400015 MEV MEV MEV MEV MEV MEV 2172200400016 1.14 2.E-02 1.14 1.E-02 1.05 2.E-022172200400017 ENDDATA 3 0 2172200400018 ENDSUBENT 17 0 2172200499999 SUBENT 21722005 20110227 22262172200500001 BIB 4 9 2172200500002 REACTION 1(25-MN-55(0,0),,TEM) Nuclear temperature. 2172200500003 2(25-MN-55(0,0),,TEM) Nuclear temperature. 2172200500004 3(25-MN-55(0,0),,TEM) Nuclear temperature. 2172200500005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200500006 2. Bjoklund-Fernbach potential. 2172200500007 3. Cross section assumed constant. 2172200500008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200500009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200500010 (20030801U) last checking has been done. 2172200500011 ENDBIB 9 0 2172200500012 NOCOMMON 0 0 2172200500013 DATA 6 1 2172200500014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200500015 MEV MEV MEV MEV MEV MEV 2172200500016 1.32 4.E-02 1.29 6.E-02 1.29 4.E-022172200500017 ENDDATA 3 0 2172200500018 ENDSUBENT 17 0 2172200599999 SUBENT 21722006 20110227 22262172200600001 BIB 4 9 2172200600002 REACTION 1(26-FE-0(0,0),,TEM) Nuclear temperature. 2172200600003 2(26-FE-0(0,0),,TEM) Nuclear temperature. 2172200600004 3(26-FE-0(0,0),,TEM) Nuclear temperature. 2172200600005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200600006 2. Bjoklund-Fernbach potential. 2172200600007 3. Cross section assumed constant. 2172200600008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200600009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200600010 (20030801U) last checking has been done. 2172200600011 ENDBIB 9 0 2172200600012 NOCOMMON 0 0 2172200600013 DATA 6 1 2172200600014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200600015 MEV MEV MEV MEV MEV MEV 2172200600016 1.2 2.E-02 1.16 2.E-02 1.15 2.E-022172200600017 ENDDATA 3 0 2172200600018 ENDSUBENT 17 0 2172200699999 SUBENT 21722007 20110227 22262172200700001 BIB 4 9 2172200700002 REACTION 1(27-CO-59(0,0),,TEM) Nuclear temperature. 2172200700003 2(27-CO-59(0,0),,TEM) Nuclear temperature. 2172200700004 3(27-CO-59(0,0),,TEM) Nuclear temperature. 2172200700005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200700006 2. Bjoklund-Fernbach potential 2172200700007 3. cross section assumed constant. 2172200700008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200700009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200700010 (20030801U) last checking has been done. 2172200700011 ENDBIB 9 0 2172200700012 NOCOMMON 0 0 2172200700013 DATA 6 1 2172200700014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200700015 MEV MEV MEV MEV MEV MEV 2172200700016 1.27 3.E-02 1.28 3.E-02 1.3 3.E-022172200700017 ENDDATA 3 0 2172200700018 ENDSUBENT 17 0 2172200799999 SUBENT 21722008 20110227 22262172200800001 BIB 4 9 2172200800002 REACTION 1(28-NI-0(0,0),,TEM) Nuclear temperature. 2172200800003 2(28-NI-0(0,0),,TEM) Nuclear temperature. 2172200800004 3(28-NI-0(0,0),,TEM) Nuclear temperature. 2172200800005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200800006 2. Bjoklund-Fernbach potential. 2172200800007 3. Cross section assumed constant. 2172200800008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200800009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200800010 (20030801U) last checking has been done. 2172200800011 ENDBIB 9 0 2172200800012 NOCOMMON 0 0 2172200800013 DATA 6 1 2172200800014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200800015 MEV MEV MEV MEV MEV MEV 2172200800016 1.2 2.E-02 1.16 2.E-02 1.16 2.E-022172200800017 ENDDATA 3 0 2172200800018 ENDSUBENT 17 0 2172200899999 SUBENT 21722009 20110227 22262172200900001 BIB 4 9 2172200900002 REACTION 1(29-CU-0(0,0),,TEM) Nuclear temperature. 2172200900003 2(29-CU-0(0,0),,TEM) Nuclear temperature. 2172200900004 3(29-CU-0(0,0),,TEM) Nuclear temperature. 2172200900005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172200900006 2. Bjoklund-Fernbach potential. 2172200900007 3. Cross section assumed constant. 2172200900008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172200900009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172200900010 (20030801U) last checking has been done. 2172200900011 ENDBIB 9 0 2172200900012 NOCOMMON 0 0 2172200900013 DATA 6 1 2172200900014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172200900015 MEV MEV MEV MEV MEV MEV 2172200900016 1.15 4.E-02 1.16 4.E-02 1.2 4.E-022172200900017 ENDDATA 3 0 2172200900018 ENDSUBENT 17 0 2172200999999 SUBENT 21722010 20110227 22262172201000001 BIB 4 9 2172201000002 REACTION 1(30-ZN-0(0,0),,TEM) Nuclear temperature. 2172201000003 2(30-ZN-0(0,0),,TEM) Nuclear temperature. 2172201000004 3(30-ZN-0(0,0),,TEM) Nuclear temperature. 2172201000005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201000006 2. Bjoklund-Fernbach potential. 2172201000007 3. Cross section assumed constant. 2172201000008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172201000009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201000010 (20030801U) last checking has been done. 2172201000011 ENDBIB 9 0 2172201000012 NOCOMMON 0 0 2172201000013 DATA 6 1 2172201000014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201000015 MEV MEV MEV MEV MEV MEV 2172201000016 1.24 2.E-02 1.27 2.E-02 1.32 2.E-022172201000017 ENDDATA 3 0 2172201000018 ENDSUBENT 17 0 2172201099999 SUBENT 21722011 20110227 22262172201100001 BIB 4 9 2172201100002 REACTION 1(32-GE-0(0,0),,TEM) Nuclear temperature. 2172201100003 2(32-GE-0(0,0),,TEM) Nuclear temperature. 2172201100004 3(32-GE-0(0,0),,TEM) Nuclear temperature. 2172201100005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201100006 2. Bjoklund-Fernbach potential. 2172201100007 3. Cross section assumed constant. 2172201100008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172201100009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201100010 (20030801U) last checking has been done. 2172201100011 ENDBIB 9 0 2172201100012 NOCOMMON 0 0 2172201100013 DATA 6 1 2172201100014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201100015 MEV MEV MEV MEV MEV MEV 2172201100016 1.21 5.E-02 1.23 5.E-02 1.24 5.E-022172201100017 ENDDATA 3 0 2172201100018 ENDSUBENT 17 0 2172201199999 SUBENT 21722012 20110227 22262172201200001 BIB 4 9 2172201200002 REACTION 1(33-AS-75(0,0),,TEM) Nuclear temperature. 2172201200003 2(33-AS-75(0,0),,TEM) Nuclear temperature. 2172201200004 3(33-AS-75(0,0),,TEM) Nuclear temperature. 2172201200005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201200006 2. Bjoklund-Fernbach potential 2172201200007 3. cross section assumed constant. 2172201200008 STATUS (TABLE) .Table 2 from NST,9,301,1973 2172201200009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201200010 (20030801U) last checking has been done. 2172201200011 ENDBIB 9 0 2172201200012 NOCOMMON 0 0 2172201200013 DATA 6 1 2172201200014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201200015 MEV MEV MEV MEV MEV MEV 2172201200016 1.16 2.E-02 1.22 2.E-02 1.24 2.E-022172201200017 ENDDATA 3 0 2172201200018 ENDSUBENT 17 0 2172201299999 SUBENT 21722013 20110227 22262172201300001 BIB 4 9 2172201300002 REACTION 1(22-TI-0(0,0),,LDP) Level density parameter. 2172201300003 2(22-TI-0(0,0),,LDP) Level density parameter. 2172201300004 3(22-TI-0(0,0),,LDP) Level density parameter. 2172201300005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201300006 2. Bjoklund-Fernbach potential. 2172201300007 3. Cross section assumed constant. 2172201300008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201300009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201300010 (20030801U) last checking has been done. 2172201300011 ENDBIB 9 0 2172201300012 NOCOMMON 0 0 2172201300013 DATA 6 1 2172201300014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201300015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201300016 8.75 2.1E-01 9.1 2.1E-01 1.091E+01 2.5E-012172201300017 ENDDATA 3 0 2172201300018 ENDSUBENT 17 0 2172201399999 SUBENT 21722014 20110227 22262172201400001 BIB 4 9 2172201400002 REACTION 1(23-V-51(0,0),,LDP) Level density parameter. 2172201400003 2(23-V-51(0,0),,LDP) Level density parameter. 2172201400004 3(23-V-51(0,0),,LDP) Level density parameter. 2172201400005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201400006 2. Bjoklund-Fernbach potential. 2172201400007 3. Cross section assumed constant. 2172201400008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201400009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201400010 (20030801U) last checking has been done. 2172201400011 ENDBIB 9 0 2172201400012 NOCOMMON 0 0 2172201400013 DATA 6 1 2172201400014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201400015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201400016 9.02 2.5E-01 9.05 2.7E-01 1.018E+01 4.E-012172201400017 ENDDATA 3 0 2172201400018 ENDSUBENT 17 0 2172201499999 SUBENT 21722015 20110227 22262172201500001 BIB 4 9 2172201500002 REACTION 1(24-CR-0(0,0),,LDP) Level density parameter. 2172201500003 2(24-CR-0(0,0),,LDP) Level density parameter. 2172201500004 3(24-CR-0(0,0),,LDP) Level density parameter. 2172201500005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201500006 2. Bjoklund-Fernbach potential. 2172201500007 3. Cross section assumed constant. 2172201500008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201500009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201500010 (20030801U) last checking has been done. 2172201500011 ENDBIB 9 0 2172201500012 NOCOMMON 0 0 2172201500013 DATA 6 1 2172201500014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201500015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201500016 9.31 2.6E-01 9.34 2.4E-01 1.05E+01 4.E-012172201500017 ENDDATA 3 0 2172201500018 ENDSUBENT 17 0 2172201599999 SUBENT 21722016 20110227 22262172201600001 BIB 4 9 2172201600002 REACTION 1(25-MN-55(0,0),,LDP) Level density parameter. 2172201600003 2(25-MN-55(0,0),,LDP) Level density parameter. 2172201600004 3(25-MN-55(0,0),,LDP) Level density parameter. 2172201600005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201600006 2. Bjoklund-Fernbach potential. 2172201600007 3. Cross section assumed constant. 2172201600008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201600009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201600010 (20030801U) last checking has been done. 2172201600011 ENDBIB 9 0 2172201600012 NOCOMMON 0 0 2172201600013 DATA 6 1 2172201600014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201600015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201600016 7.77 3.6E-01 7.99 4.E-01 8.03 4.E-012172201600017 ENDDATA 3 0 2172201600018 ENDSUBENT 17 0 2172201699999 SUBENT 21722017 20110227 22262172201700001 BIB 4 9 2172201700002 REACTION 1(26-FE-0(0,0),,LDP) Level density parameter. 2172201700003 2(26-FE-0(0,0),,LDP) Level density parameter. 2172201700004 3(26-FE-0(0,0),,LDP) Level density parameter. 2172201700005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201700006 2. Bjoklund-Fernbach potential. 2172201700007 3. Cross section assumed constant. 2172201700008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201700009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201700010 (20030801U) last checking has been done. 2172201700011 ENDBIB 9 0 2172201700012 NOCOMMON 0 0 2172201700013 DATA 6 1 2172201700014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201700015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201700016 8.54 2.2E-01 8.97 2.5E-01 9.04 2.9E-012172201700017 ENDDATA 3 0 2172201700018 ENDSUBENT 17 0 2172201799999 SUBENT 21722018 20110227 22262172201800001 BIB 4 9 2172201800002 REACTION 1(27-CO-59(0,0),,LDP) Level density parameter. 2172201800003 2(27-CO-59(0,0),,LDP) Level density parameter. 2172201800004 3(27-CO-59(0,0),,LDP) Level density parameter. 2172201800005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201800006 2. Bjoklund-Fernbach potential 2172201800007 3. cross section assumed constant. 2172201800008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201800009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201800010 (20030801U) last checking has been done. 2172201800011 ENDBIB 9 0 2172201800012 NOCOMMON 0 0 2172201800013 DATA 6 1 2172201800014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201800015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201800016 8.08 2.8E-01 8.23 2.9E-01 8.32 3.E-012172201800017 ENDDATA 3 0 2172201800018 ENDSUBENT 17 0 2172201899999 SUBENT 21722019 20110227 22262172201900001 BIB 4 9 2172201900002 REACTION 1(28-NI-0(0,0),,LDP) Level density parameter. 2172201900003 2(28-NI-0(0,0),,LDP) Level density parameter. 2172201900004 3(28-NI-0(0,0),,LDP) Level density parameter. 2172201900005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172201900006 2. Bjoklund-Fernbach potential. 2172201900007 3. Cross section assumed constant. 2172201900008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172201900009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172201900010 (20030801U) last checking has been done. 2172201900011 ENDBIB 9 0 2172201900012 NOCOMMON 0 0 2172201900013 DATA 6 1 2172201900014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172201900015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172201900016 8.72 2.9E-01 9.11 3.5E-01 9.18 3.4E-012172201900017 ENDDATA 3 0 2172201900018 ENDSUBENT 17 0 2172201999999 SUBENT 21722020 20110227 22262172202000001 BIB 4 9 2172202000002 REACTION 1(29-CU-0(0,0),,LDP) Level density parameter. 2172202000003 2(29-CU-0(0,0),,LDP) Level density parameter. 2172202000004 3(29-CU-0(0,0),,LDP) Level density parameter. 2172202000005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172202000006 2. Bjoklund-Fernbach potential. 2172202000007 3. Cross section assumed constant. 2172202000008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172202000009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172202000010 (20030801U) last checking has been done. 2172202000011 ENDBIB 9 0 2172202000012 NOCOMMON 0 0 2172202000013 DATA 6 1 2172202000014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172202000015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172202000016 9.15 4.7E-01 9.57 5.1E-01 9.72 5.5E-012172202000017 ENDDATA 3 0 2172202000018 ENDSUBENT 17 0 2172202099999 SUBENT 21722021 20110227 22262172202100001 BIB 4 9 2172202100002 REACTION 1(30-ZN-0(0,0),,LDP) Level density parameter. 2172202100003 2(30-ZN-0(0,0),,LDP) Level density parameter. 2172202100004 3(30-ZN-0(0,0),,LDP) Level density parameter. 2172202100005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172202100006 2. Bjoklund-Fernbach potential. 2172202100007 3. Cross section assumed constant. 2172202100008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172202100009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172202100010 (20030801U) last checking has been done. 2172202100011 ENDBIB 9 0 2172202100012 NOCOMMON 0 0 2172202100013 DATA 6 1 2172202100014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172202100015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172202100016 7.4 1.8E-01 7.77 1.9E-01 7.95 2.1E-012172202100017 ENDDATA 3 0 2172202100018 ENDSUBENT 17 0 2172202199999 SUBENT 21722022 20110227 22262172202200001 BIB 4 9 2172202200002 REACTION 1(32-GE-0(0,0),,LDP) Level density parameter. 2172202200003 2(32-GE-0(0,0),,LDP) Level density parameter. 2172202200004 3(32-GE-0(0,0),,LDP) Level density parameter. 2172202200005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172202200006 2. Bjoklund-Fernbach potential. 2172202200007 3. Cross section assumed constant. 2172202200008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172202200009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172202200010 (20030801U) last checking has been done. 2172202200011 ENDBIB 9 0 2172202200012 NOCOMMON 0 0 2172202200013 DATA 6 1 2172202200014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172202200015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172202200016 7.61 4.3E-01 7.69 4.5E-01 7.83 5.E-012172202200017 ENDDATA 3 0 2172202200018 ENDSUBENT 17 0 2172202299999 SUBENT 21722023 20110227 22262172202300001 BIB 4 9 2172202300002 REACTION 1(33-AS-75(0,0),,LDP) Level density parameter. 2172202300003 2(33-AS-75(0,0),,LDP) Level density parameter. 2172202300004 3(33-AS-75(0,0),,LDP) Level density parameter. 2172202300005 ANALYSIS 1. Perey-Buck potential for inverse cross section. 2172202300006 2. Bjoklund-Fernbach potential 2172202300007 3. cross section assumed constant. 2172202300008 STATUS (TABLE) .Table 3 from NST,9,301,1973 2172202300009 HISTORY (20030730A) Pointers introduced instead of flags-J.O.S2172202300010 (20030801U) last checking has been done. 2172202300011 ENDBIB 9 0 2172202300012 NOCOMMON 0 0 2172202300013 DATA 6 1 2172202300014 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32172202300015 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 1/MEV 2172202300016 8.65 1.8E-01 8.95 2.E-01 9.59 2.4E-012172202300017 ENDDATA 3 0 2172202300018 ENDSUBENT 17 0 2172202399999 SUBENT 21722024 20110227 22262172202400001 BIB 4 13 2172202400002 REACTION (22-TI-0(N,INL)22-TI-0,,DA,,4PI) 2172202400003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202400004 integration the measured neutron emission spectra over2172202400005 energy using the values given for the nuclear 2172202400006 temperature and the level density formalism. The 2172202400007 inelastic neutron spectra are extrapolated to lower 2172202400008 energies. 2172202400009 (4PI1A) The angle integrated cross section is taken 2172202400010 as the cross section at 110 degrees multiplied by 2172202400011 four pi. 2172202400012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202400013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202400014 changed on DA,,4PI; ANG added. 2172202400015 ENDBIB 13 0 2172202400016 NOCOMMON 0 0 2172202400017 DATA 4 1 2172202400018 EN ANG DATA DATA-ERR 2172202400019 MEV ADEG MB MB 2172202400020 14.1 110. 1.127E+03 1.9E+02 2172202400021 ENDDATA 3 0 2172202400022 ENDSUBENT 21 0 2172202499999 SUBENT 21722025 20110227 22262172202500001 BIB 4 13 2172202500002 REACTION (23-V-51(N,INL)23-V-51,,DA,,4PI) 2172202500003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202500004 integration the measured neutron emission spectra over2172202500005 energy using the values given for the nuclear 2172202500006 temperature and the level density formalism. The 2172202500007 inelastic neutron spectra are extrapolated to lower 2172202500008 energies. 2172202500009 (4PI1A) The angle integrated cross section is taken 2172202500010 as the cross section at 110 degrees multiplied by 2172202500011 four pi. 2172202500012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202500013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202500014 changed on DA,,4PI; ANG added. 2172202500015 ENDBIB 13 0 2172202500016 NOCOMMON 0 0 2172202500017 DATA 4 1 2172202500018 EN ANG DATA DATA-ERR 2172202500019 MEV ADEG MB MB 2172202500020 14.1 110. 1.284E+03 1.68E+02 2172202500021 ENDDATA 3 0 2172202500022 ENDSUBENT 21 0 2172202599999 SUBENT 21722026 20110227 22262172202600001 BIB 4 13 2172202600002 REACTION (24-CR-0(N,INL)24-CR-0,,DA,,4PI) 2172202600003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202600004 integration the measured neutron emission spectra over2172202600005 energy using the values given for the nuclear 2172202600006 temperature and the level density formalism. The 2172202600007 inelastic neutron spectra are extrapolated to lower 2172202600008 energies. 2172202600009 (4PI1A) The angle integrated cross section is taken 2172202600010 as the cross section at 110 degrees multiplied by 2172202600011 four pi. 2172202600012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202600013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202600014 changed on DA,,4PI; ANG added. 2172202600015 ENDBIB 13 0 2172202600016 NOCOMMON 0 0 2172202600017 DATA 4 1 2172202600018 EN ANG DATA DATA-ERR 2172202600019 MEV ADEG MB MB 2172202600020 14.1 110. 1.27E+03 1.26E+02 2172202600021 ENDDATA 3 0 2172202600022 ENDSUBENT 21 0 2172202699999 SUBENT 21722027 20110227 22262172202700001 BIB 4 13 2172202700002 REACTION (25-MN-55(N,INL)25-MN-55,,DA,,4PI) 2172202700003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202700004 integration the measured neutron emission spectra over2172202700005 energy using the values given for the nuclear 2172202700006 temperature and the level density formalism. The 2172202700007 inelastic neutron spectra are extrapolated to lower 2172202700008 energies. 2172202700009 (4PI1A) The angle integrated cross section is taken 2172202700010 as the cross section at 110 degrees multiplied by 2172202700011 four Pi. 2172202700012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202700013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202700014 changed on DA,,4PI; ANG added. 2172202700015 ENDBIB 13 0 2172202700016 NOCOMMON 0 0 2172202700017 DATA 4 1 2172202700018 EN ANG DATA DATA-ERR 2172202700019 MEV ADEG MB MB 2172202700020 14.1 110. 8.53E+02 1.35E+02 2172202700021 ENDDATA 3 0 2172202700022 ENDSUBENT 21 0 2172202799999 SUBENT 21722028 20110227 22262172202800001 BIB 4 13 2172202800002 REACTION (26-FE-0(N,INL)26-FE-0,,DA,,4PI) 2172202800003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202800004 integration the measured neutron emission spectra over2172202800005 energy using the values given for the nuclear 2172202800006 temperature and the level density formalism. The 2172202800007 inelastic neutron spectra are extrapolated to lower 2172202800008 energies. 2172202800009 (4PI1A) The angle integrated cross section is taken 2172202800010 as the cross section at 110 degrees multiplied by 2172202800011 four Pi. 2172202800012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202800013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202800014 changed on DA,,4PI; ANG added. 2172202800015 ENDBIB 13 0 2172202800016 NOCOMMON 0 0 2172202800017 DATA 4 1 2172202800018 EN ANG DATA DATA-ERR 2172202800019 MEV ADEG MB MB 2172202800020 14.1 110. 1.113E+03 1.49E+02 2172202800021 ENDDATA 3 0 2172202800022 ENDSUBENT 21 0 2172202899999 SUBENT 21722029 20110227 22262172202900001 BIB 4 13 2172202900002 REACTION (27-CO-59(N,INL)27-CO-59,,DA,,4PI) 2172202900003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172202900004 integration the measured neutron emission spectra over2172202900005 energy using the values given for the nuclear 2172202900006 temperature and the level density formalism. The 2172202900007 inelastic neutron spectra are extrapolated to lower 2172202900008 energies. 2172202900009 (4PI1A) The angle integrated cross section is taken 2172202900010 as the cross section at 110 degrees multiplied by 2172202900011 four Pi. 2172202900012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172202900013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172202900014 changed on DA,,4PI; ANG added. 2172202900015 ENDBIB 13 0 2172202900016 NOCOMMON 0 0 2172202900017 DATA 4 1 2172202900018 EN ANG DATA DATA-ERR 2172202900019 MEV ADEG MB MB 2172202900020 14.1 110. 1.067E+03 1.95E+02 2172202900021 ENDDATA 3 0 2172202900022 ENDSUBENT 21 0 2172202999999 SUBENT 21722030 20110227 22262172203000001 BIB 4 13 2172203000002 REACTION (28-NI-0(N,INL)28-NI-0,,DA,,4PI) 2172203000003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172203000004 integration the measured neutron emission spectra over2172203000005 energy using the values given for the nuclear 2172203000006 temperature and the level density formalism. The 2172203000007 inelastic neutron spectra are extrapolated to lower 2172203000008 energies. 2172203000009 (4PI1A) The angle integrated cross section is taken 2172203000010 as the cross section at 110 degrees multiplied by 2172203000011 four Pi. 2172203000012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172203000013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172203000014 changed on DA,,4PI; ANG added. 2172203000015 ENDBIB 13 0 2172203000016 NOCOMMON 0 0 2172203000017 DATA 4 1 2172203000018 EN ANG DATA DATA-ERR 2172203000019 MEV ADEG MB MB 2172203000020 14.1 110. 7.66E+02 7.8E+01 2172203000021 ENDDATA 3 0 2172203000022 ENDSUBENT 21 0 2172203099999 SUBENT 21722031 20110227 22262172203100001 BIB 4 13 2172203100002 REACTION (29-CU-0(N,INL)29-CU-0,,DA,,4PI) 2172203100003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172203100004 integration the measured neutron emission spectra over2172203100005 energy using the values given for the nuclear 2172203100006 temperature and the level density formalism. The 2172203100007 inelastic neutron spectra are extrapolated to lower 2172203100008 energies. 2172203100009 (4PI1A) The angle integrated cross section is taken 2172203100010 as the cross section at 110 degrees multiplied by 2172203100011 four Pi. 2172203100012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172203100013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172203100014 changed on DA,,4PI; ANG added. 2172203100015 ENDBIB 13 0 2172203100016 NOCOMMON 0 0 2172203100017 DATA 4 1 2172203100018 EN ANG DATA DATA-ERR 2172203100019 MEV ADEG MB MB 2172203100020 14.1 110. 8.79E+02 1.07E+02 2172203100021 ENDDATA 3 0 2172203100022 ENDSUBENT 21 0 2172203199999 SUBENT 21722032 20110227 22262172203200001 BIB 4 13 2172203200002 REACTION (30-ZN-0(N,INL)30-ZN-0,,DA,,4PI) 2172203200003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172203200004 integration the measured neutron emission spectra over2172203200005 energy using the values given for the nuclear 2172203200006 temperature and the level density formalism. The 2172203200007 inelastic neutron spectra are extrapolated to lower 2172203200008 energies. 2172203200009 (4PI1A) The angle integrated cross section is taken 2172203200010 as the cross section at 110 degrees multiplied by 2172203200011 four Pi. 2172203200012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172203200013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172203200014 changed on DA,,4PI; ANG added. 2172203200015 ENDBIB 13 0 2172203200016 NOCOMMON 0 0 2172203200017 DATA 4 1 2172203200018 EN ANG DATA DATA-ERR 2172203200019 MEV ADEG MB MB 2172203200020 14.1 110. 9.15E+02 8.4E+01 2172203200021 ENDDATA 3 0 2172203200022 ENDSUBENT 21 0 2172203299999 SUBENT 21722033 20110227 22262172203300001 BIB 4 13 2172203300002 REACTION (32-GE-0(N,INL)32-GE-0,,DA,,4PI) 2172203300003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172203300004 integration the measured neutron emission spectra over2172203300005 energy using the values given for the nuclear 2172203300006 temperature and the level density formalism. The 2172203300007 inelastic neutron spectra are extrapolated to lower 2172203300008 energies. 2172203300009 (4PI1A) The angle integrated cross section is taken 2172203300010 as the cross section at 110 degrees multiplied by 2172203300011 four Pi. 2172203300012 STATUS (TABLE) .Table 5, col.1 from NST,9,301,1973 2172203300013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172203300014 changed on DA,,4PI; ANG added. 2172203300015 ENDBIB 13 0 2172203300016 NOCOMMON 0 0 2172203300017 DATA 4 1 2172203300018 EN ANG DATA DATA-ERR 2172203300019 MEV ADEG MB MB 2172203300020 14.1 110. 9.96E+02 1.59E+02 2172203300021 ENDDATA 3 0 2172203300022 ENDSUBENT 21 0 2172203399999 SUBENT 21722034 20110227 22262172203400001 BIB 4 13 2172203400002 REACTION (33-AS-75(N,INL)33-AS-75,,DA,,4PI) 2172203400003 ANALYSIS (INTED) Cross sections at 110 degrees are derived by 2172203400004 integration the measured neutron emission spectra over2172203400005 energy using the values given for the nuclear 2172203400006 temperature and the level density formalism. The 2172203400007 inelastic neutron spectra are extrapolated to lower 2172203400008 energies. 2172203400009 (4PI1A) The angle integrated cross section is taken 2172203400010 as the cross section at 110 degrees multiplied by 2172203400011 four Pi. 2172203400012 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172203400013 HISTORY (20110301A) SD: REACTION code corrected: SF6=SIG 2172203400014 changed on DA,,4PI; ANG added. 2172203400015 ENDBIB 13 0 2172203400016 NOCOMMON 0 0 2172203400017 DATA 4 1 2172203400018 EN ANG DATA DATA-ERR 2172203400019 MEV ADEG MB MB 2172203400020 14.1 110. 1.368E+03 1.28E+02 2172203400021 ENDDATA 3 0 2172203400022 ENDSUBENT 21 0 2172203499999 SUBENT 21722035 20110227 22262172203500001 BIB 4 9 2172203500002 REACTION (22-TI-0(N,EL)22-TI-0,,DA) Differential elastic cross 2172203500003 section at 110 degrees. 2172203500004 ANALYSIS .Differential elastic cross sections are derived from 2172203500005 measured neutron spectra. 2172203500006 COMMENT .These measurements are given as a check of the 2172203500007 reliability of the inelastic cross sections. 2172203500008 .The values given may include some contributions from 2172203500009 low lying excited levels. 2172203500010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172203500011 ENDBIB 9 0 2172203500012 NOCOMMON 0 0 2172203500013 DATA 4 1 2172203500014 EN ANG DATA DATA-ERR 2172203500015 MEV ADEG MB/SR PER-CENT 2172203500016 14.1 1.1E+02 1.99E+01 8. 2172203500017 ENDDATA 3 0 2172203500018 ENDSUBENT 17 0 2172203599999 SUBENT 21722036 20110227 22262172203600001 BIB 4 9 2172203600002 REACTION (23-V-51(N,EL)23-V-51,,DA) Differential elastic cross 2172203600003 section at 110 degrees. 2172203600004 ANALYSIS .Differential elastic cross sections are derived from 2172203600005 measured neutron spectra. 2172203600006 COMMENT .These measurements are given as a check of the 2172203600007 reliability of the inelastic cross sections. 2172203600008 .The values given may include some contributions from 2172203600009 low lying excited levels. 2172203600010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172203600011 ENDBIB 9 0 2172203600012 NOCOMMON 0 0 2172203600013 DATA 4 1 2172203600014 EN ANG DATA DATA-ERR 2172203600015 MEV ADEG MB/SR PER-CENT 2172203600016 14.1 1.1E+02 2.2E+01 8. 2172203600017 ENDDATA 3 0 2172203600018 ENDSUBENT 17 0 2172203699999 SUBENT 21722037 20110227 22262172203700001 BIB 4 9 2172203700002 REACTION (24-CR-0(N,EL)24-CR-0,,DA) Differential elastic cross 2172203700003 section at 110 degrees. 2172203700004 ANALYSIS .Differential elastic cross sections are derived from 2172203700005 measured neutron spectra. 2172203700006 COMMENT .These measurements are given as a check of the 2172203700007 reliability of the inelastic cross sections. 2172203700008 .The values given may include some contributions from 2172203700009 low lying excited levels. 2172203700010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172203700011 ENDBIB 9 0 2172203700012 NOCOMMON 0 0 2172203700013 DATA 4 1 2172203700014 EN ANG DATA DATA-ERR 2172203700015 MEV ADEG MB/SR PER-CENT 2172203700016 14.1 1.1E+02 1.87E+01 8. 2172203700017 ENDDATA 3 0 2172203700018 ENDSUBENT 17 0 2172203799999 SUBENT 21722038 20230211 20231011 2172203800001 BIB 7 13 2172203800002 REACTION (25-MN-55(N,EL)25-MN-55,EXL,DA) 2172203800003 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 2172203800004 CRITIQUE S.Simakov (2022-08-06): possible inclusion of inelastic2172203800005 scattering below Ex~3.3 to 4.2 MeV 2172203800006 ANALYSIS Differential elastic cross sections are derived from 2172203800007 measured neutron spectra. 2172203800008 COMMENT These measurements are given as a check of the 2172203800009 reliability of the inelastic cross sections. 2172203800010 The values given may include some contributions from 2172203800011 low lying excited levels. 2172203800012 STATUS (TABLE) Table 6 from Nucl.Sci.Tech.,9,301,1973 2172203800013 HISTORY (20230211A) SD: SF5=EXL added to REACTION code. 2172203800014 CRITIQUE and REL-REF added. 2172203800015 ENDBIB 13 0 2172203800016 NOCOMMON 0 0 2172203800017 DATA 4 1 2172203800018 EN ANG DATA DATA-ERR 2172203800019 MEV ADEG MB/SR PER-CENT 2172203800020 14.1 110. 18.2 8. 2172203800021 ENDDATA 3 0 2172203800022 ENDSUBENT 21 0 2172203899999 SUBENT 21722039 20110227 22262172203900001 BIB 4 9 2172203900002 REACTION (26-FE-0(N,EL)26-FE-0,,DA) Differential elastic cross 2172203900003 section at 110 degrees. 2172203900004 ANALYSIS .Differential elastic cross sections are derived from 2172203900005 measured neutron spectra. 2172203900006 COMMENT .These measurements are given as a check of the 2172203900007 reliability of the inelastic cross sections. 2172203900008 .The values given may include some contributions from 2172203900009 low lying excited levels. 2172203900010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172203900011 ENDBIB 9 0 2172203900012 NOCOMMON 0 0 2172203900013 DATA 4 1 2172203900014 EN ANG DATA DATA-ERR 2172203900015 MEV ADEG MB/SR PER-CENT 2172203900016 14.1 1.1E+02 1.05E+01 8. 2172203900017 ENDDATA 3 0 2172203900018 ENDSUBENT 17 0 2172203999999 SUBENT 21722040 20110227 22262172204000001 BIB 4 9 2172204000002 REACTION (27-CO-59(N,EL)27-CO-59,,DA) Differential elastic cross2172204000003 section at 110 degrees. 2172204000004 ANALYSIS .Differential elastic cross sections are derived from 2172204000005 measured neutron spectra. 2172204000006 COMMENT .These measurements are given as a check of the 2172204000007 reliability of the inelastic cross sections. 2172204000008 .The values given may include some contributions from 2172204000009 low lying excited levels. 2172204000010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172204000011 ENDBIB 9 0 2172204000012 NOCOMMON 0 0 2172204000013 DATA 4 1 2172204000014 EN ANG DATA DATA-ERR 2172204000015 MEV ADEG MB/SR PER-CENT 2172204000016 14.1 1.1E+02 1.64E+01 8. 2172204000017 ENDDATA 3 0 2172204000018 ENDSUBENT 17 0 2172204099999 SUBENT 21722041 20110227 22262172204100001 BIB 4 9 2172204100002 REACTION (28-NI-0(N,EL)28-NI-0,,DA) Differential elastic cross 2172204100003 section at 110 degrees. 2172204100004 ANALYSIS .Differential elastic cross sections are derived from 2172204100005 measured neutron spectra. 2172204100006 COMMENT .These measurements are given as a check of the 2172204100007 reliability of the inelastic cross sections. 2172204100008 .The values given may include some contributions from 2172204100009 low lying excited levels. 2172204100010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172204100011 ENDBIB 9 0 2172204100012 NOCOMMON 0 0 2172204100013 DATA 4 1 2172204100014 EN ANG DATA DATA-ERR 2172204100015 MEV ADEG MB/SR PER-CENT 2172204100016 14.1 1.1E+02 1.08E+01 8. 2172204100017 ENDDATA 3 0 2172204100018 ENDSUBENT 17 0 2172204199999 SUBENT 21722042 20110227 22262172204200001 BIB 4 9 2172204200002 REACTION (29-CU-0(N,EL)29-CU-0,,DA) Differential elastic cross 2172204200003 section at 110 degrees. 2172204200004 ANALYSIS .Differential elastic cross sections are derived from 2172204200005 measured neutron spectra. 2172204200006 COMMENT .These measurements are given as a check of the 2172204200007 reliability of the inelastic cross sections. 2172204200008 .The values given may include some contributions from 2172204200009 low lying excited levels. 2172204200010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172204200011 ENDBIB 9 0 2172204200012 NOCOMMON 0 0 2172204200013 DATA 4 1 2172204200014 EN ANG DATA DATA-ERR 2172204200015 MEV ADEG MB/SR PER-CENT 2172204200016 14.1 1.1E+02 1.12E+01 8. 2172204200017 ENDDATA 3 0 2172204200018 ENDSUBENT 17 0 2172204299999 SUBENT 21722043 20110227 22262172204300001 BIB 4 9 2172204300002 REACTION (30-ZN-0(N,EL)30-ZN-0,,DA) Differential elastic cross 2172204300003 section at 110 degrees. 2172204300004 ANALYSIS .Differential elastic cross sections are derived from 2172204300005 measured neutron spectra. 2172204300006 COMMENT .These measurements are given as a check of the 2172204300007 reliability of the inelastic cross sections. 2172204300008 .The values given may include some contributions from 2172204300009 low lying excited levels. 2172204300010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172204300011 ENDBIB 9 0 2172204300012 NOCOMMON 0 0 2172204300013 DATA 4 1 2172204300014 EN ANG DATA DATA-ERR 2172204300015 MEV ADEG MB/SR PER-CENT 2172204300016 14.1 1.1E+02 1.55E+01 8. 2172204300017 ENDDATA 3 0 2172204300018 ENDSUBENT 17 0 2172204399999 SUBENT 21722044 20110227 22262172204400001 BIB 4 9 2172204400002 REACTION (32-GE-0(N,EL)32-GE-0,,DA) Differential elastic cross 2172204400003 section at 110 degrees. 2172204400004 ANALYSIS .Differential elastic cross sections are derived from 2172204400005 measured neutron spectra. 2172204400006 COMMENT .These measurements are given as a check of the 2172204400007 reliability of the inelastic cross sections. 2172204400008 .The values given may include some contributions from 2172204400009 low lying excited levels. 2172204400010 STATUS (TABLE) .Table 6 from NST,9,301,1973 2172204400011 ENDBIB 9 0 2172204400012 NOCOMMON 0 0 2172204400013 DATA 4 1 2172204400014 EN ANG DATA DATA-ERR 2172204400015 MEV ADEG MB/SR PER-CENT 2172204400016 14.1 1.1E+02 1.58E+01 8. 2172204400017 ENDDATA 3 0 2172204400018 ENDSUBENT 17 0 2172204499999 SUBENT 21722045 20230211 20231011 2172204500001 BIB 7 13 2172204500002 REACTION (33-AS-75(N,EL)33-AS-75,EXL,DA) 2172204500003 REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 2172204500004 CRITIQUE S.Simakov (2022-08-06): possible inclusion of inelastic2172204500005 scattering below Ex~3.3 to 4.2 MeV 2172204500006 ANALYSIS Differential elastic cross sections are derived from 2172204500007 measured neutron spectra. 2172204500008 COMMENT These measurements are given as a check of the 2172204500009 reliability of the inelastic cross sections. 2172204500010 The values given may include some contributions from 2172204500011 low lying excited levels. 2172204500012 STATUS (TABLE) Table 6 from Nucl.Sci.Tech.,9,301,1973 2172204500013 HISTORY (20230211A) SD: SF5=EXL added to REACTION code. 2172204500014 CRITIQUE and REL-REF added. 2172204500015 ENDBIB 13 0 2172204500016 NOCOMMON 0 0 2172204500017 DATA 4 1 2172204500018 EN ANG DATA DATA-ERR 2172204500019 MEV ADEG MB/SR PER-CENT 2172204500020 14.1 110. 18. 8. 2172204500021 ENDDATA 3 0 2172204500022 ENDSUBENT 21 0 2172204599999 ENDENTRY 3 0 2172299999999