28-Ni-nat from T512 512 0 0 0 2.80000+ 4 5.81826+ 1 1 0 0 11328 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 01328 1451 2 0.00000+ 0 0.00000+ 0 0 0 265 1251328 1451 3 28-ni bnl(nndc) eval-mar77 m.divadeenam 1328 1451 4 dist-jan79 781130 1328 1451 5 neutron and gamma production cross-sections are given from 1328 1451 6 1.0e-05ev to 20.0mev. 1328 1451 7 ** ** ** ** ** ** **1328 1451 8 (n,n ) and (n,particle) cross-sections are constructed from ni 1328 1451 9 isotopic contributions weighted with the corresponding natural 1328 1451 10 abundances. 1328 1451 11 ** *** ** *** *** *** 1328 1451 12 summary *********** 1328 1451 13 *****************************************************************1328 1451 14 file 2- resonance parameters *same as endf-iv 1328 1451 15 1328 1451 16 file 3 ------- 1328 1451 17 mt = 1 total cross section *new 1328 1451 18 mt = 2 elastic cross section *almost same as endf-iv 1328 1451 19 mt = 3 nonelastic cross section*almost same as endf-iv 1328 1451 20 except for the structure 1328 1451 21 in some of the reaction 1328 1451 22 channels 1328 1451 23 mt = 4 total inelastic *new 1328 1451 24 mt = 16 (n,2n) cross section *same as endf-iv 1328 1451 25 except for the threshold 1328 1451 26 region 1328 1451 27 mt = 22 (n,an)+(n,na) *new 1328 1451 28 mt = 28 (n,pn)+(n,np) *new 1328 1451 29 mt = 51-76 discrete inelastic *new 1328 1451 30 mt = 91 inelastic continuum *new 1328 1451 31 mt = 102 radiative capture *same as endf-iv 1328 1451 32 mt = 103 (n,p) cross section *new 1328 1451 33 mt = 104 (n,d) cross section *new 1328 1451 34 mt = 107 (n,a) cross section *new 1328 1451 35 mt = 111 (n,2p) cross section *new 1328 1451 36 file 4 -------- 1328 1451 37 mt = elastic ang. distributions*endf-iv updated 1328 1451 38 mt = 51-76 inelastic angular * 1328 1451 39 distributions *new 1328 1451 40 mt = 91 continuum neutron ang. * 1328 1451 41 distributions *same as endf-iv 1328 1451 42 file 5 ------- 1328 1451 43 mt = 16, 22, 28, and 91 * 1328 1451 44 secondary neutron * 1328 1451 45 enegy distributions *new 1328 1451 46 files 12,13,14,15-------- *endf-iv updated with the 1328 1451 47 *new thermal results 1328 1451 48 ********************************************************** 1328 1451 49 ** ** ** ** ** ** **1328 1451 50 file=2 resonance parameters 1328 1451 51 --------------------------- 1328 1451 52 resonance parameters and background cross-sections from 1.0e-05ev1328 1451 53 to 690.0kev taken unchanged from mat=1190 ni evaluation of endf/b1328 1451 54 -iv library. (ref. 49) 1328 1451 55 ** ** ** ** ** ** **1328 1451 56 file=3 neutron induced cross-sections 1328 1451 57 -------------------------------- 1328 1451 58 mt=1 total cross-section from 690.0kev to 20.0mev based on the 1328 1451 59 ornl data of perey love and kinney(ref.1). a spline fit was 1328 1451 60 made both for thin and thick sample data. 1328 1451 61 for thin and thick sample data. 1328 1451 62 mt=2 elastic cross section by subtracting non-elastic(ref.2-14) 1328 1451 63 from total cross-section and supplementing with model(ref. 1328 1451 64 15 ) calculations 1328 1451 65 mt=4 total inelastic sum of discrete level excitation functio-1328 1451 66 ns and the continuum cross section. 1328 1451 67 mt=16 (n,2n) cross section ni-58 (n,2n) cross section evaluated 1328 1451 68 from the available experimental data(ref.16-25).for the 1328 1451 69 rest of the ni isotopes model(ref.27) calculations were 1328 1451 70 normalized to thresh(ref.28) calculations a 14.0mev. 1328 1451 71 mt=22 (n,an)+(n,na) the model calculated sum (n,a)+(n,an)+(n,na)1328 1451 72 for each isotope were used to calculate fission spectrum 1328 1451 73 average with the code interx(ref.29).the average cross sect-1328 1451 74 ions were normalized to the measured fission spectrum data 1328 1451 75 (ref.30).the individual isotopic model calculated excitation1328 1451 76 functions were renormalized with the corresponding normali- 1328 1451 77 zation factor.the resulting (n,an) and (n,na) excitation 1328 1451 78 functions were added to construct mt=22 file. 1328 1451 79 mt=28 (n,pn)+(n,np) the model(ref.27) calculated sum (n,d)+ 1328 1451 80 (n,pn)+(n,np) were normalized to the corresponding experime-1328 1451 81 ntal(average of different measurements) data(ref.30-37) 1328 1451 82 around 14mev neutron energy.the resulting normalization 1328 1451 83 factor was used to renormalize the individual model calcula-1328 1451 84 tion components (n,d),(n,pn) and (n,np) for ni-58 and ni-60.1328 1451 85 model (ref.27) calculate results were used for the three 1328 1451 86 minor isotopes. 1328 1451 87 mt=51-76 discrete level inelastic cross section experimental data1328 1451 88 (ref.38-46) supplemented with model(comnuc ref.47)calculated1328 1451 89 excitation functions after normalization beyond 7.0 mev.jpx 1328 1451 90 (ref.48) calculated results were used beyond 10.0mev for the1328 1451 91 first two excited levels for the even mass ni isotopes. 1328 1451 92 mt=91 inelastic cross section to the continuum of levls this was 1328 1451 93 obtained by subtracting the sum of (n,particle) cross sect- 1328 1451 94 ion including the inelastic cross section(sum) to the 1328 1451 95 discrete levels plus the capture cross section(mt=102) from 1328 1451 96 the non-elastic cross section. 1328 1451 97 mt=102 radiative capture cross section upto 690.0kev is given by 1328 1451 98 the resonance parameters in file2.from 690.0kev to 20mev 1328 1451 99 was taken from the corresponding file in endf/b-iv(ref.49). 1328 1451 100 mt=103 (n,p) cross section 1328 1451 101 ni-58 (n,p) excitation function was evaluated from exte 1328 1451 102 nsive experimental data(ref.18,23,35,50-65). 1328 1451 103 ni-60 (n,p) cross section was evaluated from experiment-1328 1451 104 al data(ref.31,37,66-75).the structure suggested by the 1328 1451 105 data(ref.68) was retained on the basis of theoretical 1328 1451 106 predictions(ref.76,77).model(ref.27) calculated cross 1328 1451 107 sections were normalized around 6.0mev to obtain the 1328 1451 108 evaluated curve around the threshold region. 1328 1451 109 ni-61,62 and 64 experimental cross sections around 14.0 1328 1451 110 mev were used to normalize the model(ref.27) predicted 1328 1451 111 cross sections. 1328 1451 112 mt=104 (n,d) cross section refer to m=28 comments. 1328 1451 113 mt=107 (n,a) cross section refer to mt=22 comments. 1328 1451 114 mt=111 (n,2p) model calculated cross sections for ni-58.assumed 1328 1451 115 it to be negligible for the remaining isotopes due to thres-1328 1451 116 hold/abundance considerations. 1328 1451 117 mt=251-253 file4 mt=2 angular distributions were used as input 1328 1451 118 data to the code dummy5(ref.79). 1328 1451 119 file=4 angular distribution of secondary neutrons 1328 1451 120 -------------------------------------------------- 1328 1451 121 mt=2 elastic scattering angular distributions based on new 1328 1451 122 experimental data(ref.46) and as given in endf/b-iv(ref. 1328 1451 123 49).legendre coefficients were generated with nuchad(ref.80)1328 1451 124 mt=16 (n,2n) angular distribution assumed isotropic 1328 1451 125 mt=22 (n,an)+(n,an) angular distribution assumed isotropic 1328 1451 126 mt=28 (n,pn)+(n,np) angular distribution assumed isotropic 1328 1451 127 mt=51-76 discrete level inelastic angular distribution compound 1328 1451 128 contribution from model(ref.47) calculated results and dire-1328 1451 129 ct part from jpx(ref.48) predictions.the two components were1328 1451 130 combined for the first two excited states for the even-even 1328 1451 131 ni isotopes.comnuc(ref.47) results were used for the higher 1328 1451 132 excited states of even isotopes and for all excited states 1328 1451 133 (considered) of the odd ni isotope.legendre coefficients 1328 1451 134 were generated with nuchad(ref.80) 1328 1451 135 mt=91 continuum secondary neutron angular distribution assumed 1328 1451 136 isotropic. 1328 1451 137 file=5 energy distribution of secondary neutrons 1328 1451 138 -------------------------------------------------- 1328 1451 139 mt=16,22,28 energy distribution expressed in terms of temperature1328 1451 140 obtained from theta(ref.81). 1328 1451 141 mt=91 continuum secondary neutron spectra model(ref.82,83) calcu-1328 1451 142 lated pre-compound fractions as a function of neutron energy1328 1451 143 were used to combine the compound and pre-equilibrium compo-1328 1451 144 nent spectra. 1328 1451 145 file=12 gamma-ray multiplicities 1328 1451 146 -------------------------------------------------- 1328 1451 147 mt=102 the multiplicities at 1.0-5 ev and thermal energy were 1328 1451 148 constructed from the combined data of maerker(ref.84a 1328 1451 149 1.0