JENDL-5 (Neutron sublibrary (activation cs)) H - 3 0 0 0 0 1.003000+3 2.989596+0 0 0 6 1 131 1451 1 0.000000+0 1.000000+0 0 0 0 6 131 1451 2 1.000000+0 2.000000+7 0 0 10 5 131 1451 3 2.936000+2 0.000000+0 4 0 96 4 131 1451 4 1-H - 3 LANL EVAL-NOV01 G.M.Hale 131 1451 5 DIST-DEC21 20211105 131 1451 6 ----JENDL-5 MATERIAL 131 131 1451 7 -----INCIDENT NEUTRON DATA 131 1451 8 ------ENDF-6 FORMAT 131 1451 9 131 1451 10 History 131 1451 11 21-11 JENDL-5b3 revised by N.Iwamoto 131 1451 12 Data taken from ENDF/B-VIII.0. 131 1451 13 21-11 revised by O.Iwamoto 131 1451 14 (MF8/MT16) added 131 1451 15 131 1451 16 *** (n,2n) replaced by ENDF/B-VI.8, total adjusted (NNDC/2010/06 * 131 1451 17 n-t scattering evaluation, based on an R-matrix analysis of p-3He 131 1451 18 scattering that was transformed from the 4Li system to the 4H 131 1451 19 system by moving all the eigenenergies downward by a Coulomb 131 1451 20 energy shift of 0.86 MeV. The calculated neutron total cross 131 1451 21 section then agreed well with new measurements [1] by Phillips et 131 1451 22 al, and the coherent scattering length with a new measurement [2] 131 1451 23 from Rauch, as was described in ref. [3]. The parameters of the 131 1451 24 fit have been used to calculate total cross sections and elastic 131 1451 25 cross sections and angular distributions in the energy range from 131 1451 26 10^(-5) eV to 20 MeV. Some allowance was made for the (n,2n) 131 1451 27 breakup cross section at energies above 8.4 MeV, so that the total 131 1451 28 cross section exceeds the elastic cross section in that energy 131 1451 29 region. 131 1451 30 ***************************************************************** 131 1451 31 MF=1 131 1451 32 MT=451 Nuclear mass = 3.01550116 131 1451 33 131 1451 34 131 1451 35 131 1451 36 MF=2 131 1451 37 131 1451 38 MT=151 Scattering length=0.36399 X 10^(-12) cm 131 1451 39 131 1451 40 MF=3 131 1451 41 MT=1 Total cross sections: calculated from 131 1451 42 R-matrix parameters after adjusting the 131 1451 43 Coulomb energy shift to agree with the 131 1451 44 measurements of ref [1], which disagree 131 1451 45 significantly with earlier data [4] at 131 1451 46 low energies. 131 1451 47 131 1451 48 MT=2. Elastic scattering cross sections: 131 1451 49 calculated from the n-t R-matrix 131 1451 50 parameters described above. Identical 131 1451 51 with MT=1 at energies below 8.4 MeV. 131 1451 52 131 1451 53 MT=16 (n,2n) cross sections: non-zero cross 131 1451 54 section obtained from allowing two-body 131 1451 55 nn-d and nn-d0 absorption channels to 131 1451 56 couple to the n-t states. This method 131 1451 57 probably underestimates the amount of 131 1451 58 (n,2n) cross section at energies above 131 1451 59 8.4 MeV. 131 1451 60 NOT GIVEN IN MF=3: 131 1451 61 131 1451 62 MT=17 (n,3n) cross section: no data given 131 1451 63 since estimates from isospin con- 131 1451 64 siderations give essentially zero 131 1451 65 probabilities. 131 1451 66 131 1451 67 MT=102 radiative capture cross section: The 131 1451 68 measured cross section is less than or 131 1451 69 equal to 6.7 microbarns at thermal. 131 1451 70 Since the Q-value is uncertain, but 131 1451 71 either zero or negative, this cross 131 1451 72 section assumed zero at all energies. 131 1451 73 131 1451 74 MF=4 131 1451 75 MT=2 Neutron elastic angular distributions 131 1451 76 in the center-of-mass system: given as 131 1451 77 Legendre coefficients calculated from 131 1451 78 the n-t R-matrix parameters. 131 1451 79 131 1451 80 131 1451 81 NOT GIVEN: MF=12, 13, 14, AND 15 131 1451 82 *************************************************************** 131 1451 83 Only radiative capture produces gamma 131 1451 84 rays. Since the capture cross section 131 1451 85 is assumed zero at all energies, these 131 1451 86 files are purposely left empty. 131 1451 87 131 1451 88 131 1451 89 REFERENCES 131 1451 90 131 1451 91 [1] T.W. Phillips, B.L. Berman and J.D. Seagrave, Phys. Rev. C 22, 131 1451 92 384 (1980). 131 1451 93 [2] H. Rauch, D. Tuppinger, H. Wolwitsch and T. Wroblewski, Phys. 131 1451 94 Lett. 165B, 39 (1985). 131 1451 95 [3] G.M. Hale, D.C. Dodder, J.D. Seagrave, B.L. Berman and T.W. 131 1451 96 Phillips, Phys. Rev. C 42, 438 (1990). 131 1451 97 [4] Los Alamos Physics and Cryogenics Group, Nucl. Phys. 12, 291 131 1451 98 (1959). 131 1451 99 131 1451 100 1 451 104 1 131 1451 101 2 151 4 1 131 1451 102 3 16 30 1 131 1451 103 8 16 2 1 131 1451 104 131 1 099999 131 0 0 0 1.003000+3 2.989596+0 0 0 1 0 131 2151 1 1.003000+3 1.000000+0 0 0 1 0 131 2151 2 1.000000-5 2.000000+7 0 0 0 0 131 2151 3 5.000000-1 3.639897-1 0 0 0 0 131 2151 4 131 2 099999 131 0 0 0 1.003000+3 2.989596+0 0 0 0 0 131 3 16 1 -6.257557+6-6.257557+6 0 0 1 81 131 3 16 2 81 2 131 3 16 3 8.350000+6 0.000000+0 8.380000+6 1.000000-3 8.381250+6 1.058900-3 131 3 16 4 8.382421+6 1.117300-3 8.383521+6 1.175000-3 8.384551+6 1.231800-3 131 3 16 5 8.386481+6 1.345800-3 8.388171+6 1.454100-3 8.389640+6 1.556000-3 131 3 16 6 8.390941+6 1.651000-3 8.392071+6 1.738900-3 8.393062+6 1.819600-3 131 3 16 7 8.394800+6 1.970000-3 8.396101+6 2.090900-3 8.398050+6 2.286300-3 131 3 16 8 8.400001+6 2.500000-3 8.406221+6 2.653800-3 8.412051+6 2.806700-3 131 3 16 9 8.417521+6 2.957900-3 8.422651+6 3.107100-3 8.427461+6 3.253800-3 131 3 16 10 8.436501+6 3.547800-3 8.444411+6 3.826700-3 8.451340+6 4.088700-3 131 3 16 11 8.457400+6 4.332600-3 8.462722+6 4.558000-3 8.472021+6 4.980900-3 131 3 16 12 8.479011+6 5.323600-3 8.484250+6 5.596100-3 8.492121+6 6.031100-3 131 3 16 13 8.500000+6 6.500000-3 8.512442+6 6.980500-3 8.523332+6 7.430000-3 131 3 16 14 8.532882+6 7.847000-3 8.541241+6 8.231000-3 8.555890+6 8.948800-3 131 3 16 15 8.566901+6 9.527901-3 8.575161+6 9.986699-3 8.587570+6 1.071700-2 131 3 16 16 8.600000+6 1.150000-2 8.637261+6 1.258600-2 8.665311+6 1.346800-2 131 3 16 17 8.686400+6 1.416900-2 8.718140+6 1.529000-2 8.750000+6 1.650000-2 131 3 16 18 8.780871+6 1.729100-2 8.835140+6 1.876800-2 8.876071+6 1.995800-2 131 3 16 19 8.937820+6 2.188600-2 9.000000+6 2.400000-2 9.061861+6 2.558600-2 131 3 16 20 9.108531+6 2.684400-2 9.178991+6 2.884700-2 9.250000+6 3.100000-2 131 3 16 21 9.374171+6 3.317400-2 9.500000+6 3.550000-2 9.622611+6 3.756300-2 131 3 16 22 9.809490+6 4.088500-2 1.000000+7 4.450000-2 1.025000+7 4.750000-2 131 3 16 23 1.050000+7 4.950000-2 1.075000+7 5.070000-2 1.100000+7 5.160000-2 131 3 16 24 1.130000+7 5.220000-2 1.150000+7 5.250000-2 1.200000+7 5.250000-2 131 3 16 25 1.250000+7 5.220000-2 1.300000+7 5.160000-2 1.350000+7 5.090000-2 131 3 16 26 1.400000+7 5.000000-2 1.410000+7 4.970000-2 1.450000+7 4.880000-2 131 3 16 27 1.500000+7 4.760000-2 1.550000+7 4.640000-2 1.600000+7 4.500000-2 131 3 16 28 1.673320+7 4.284900-2 1.750000+7 4.080000-2 1.795680+7 3.943300-2 131 3 16 29 1.866450+7 3.746700-2 1.940000+7 3.560000-2 2.000000+7 3.380000-2 131 3 16 30 131 3 099999 131 0 0 0 1.003000+3 2.989596+0 0 0 1 1 131 8 16 1 1.002000+3 0.000000+0 3 0 0 0 131 8 16 2 131 8 099999 131 0 0 0 0 0 0 0 -1 0 0 0