JENDL-5 (Neutron sublibrary (activation cs)) B - 11 0 0 0 0 5.011000+3 1.091470+1 0 0 6 1 528 1451 1 0.000000+0 0.000000+0 0 0 0 6 528 1451 2 1.000000+0 2.000000+7 0 0 10 5 528 1451 3 2.936000+2 0.000000+0 4 0 236 26 528 1451 4 5-B - 11 JAERI EVAL-MAY88 T.FUKAHORI 528 1451 5 JAERI-M 89-046 DIST-DEC21 20090831 528 1451 6 ----JENDL-5 MATERIAL 528 528 1451 7 -----INCIDENT NEUTRON DATA 528 1451 8 ------ENDF-6 FORMAT 528 1451 9 528 1451 10 HISTORY 528 1451 11 87-03 Newly evaluated by T.Fukahori (jaeri) 528 1451 12 88-05 Revised by T.Fukahori (jaeri) 528 1451 13 (n,d),(n,nd),(n,t),(n,nt) and (n,n2a) added 528 1451 14 01-07 Total cross section was revised above 14 MeV. 528 1451 15 Compiled by K.Shibata for JENDL-3.3. 528 1451 16 ***** modified parts for JENDL-3.3 ********************** 528 1451 17 (1,451) Updated. 528 1451 18 (3,1) Revised above 14 MeV. 528 1451 19 (3,2) Re-calculated. 528 1451 20 (3,251) Deleted. 528 1451 21 (4,2) Transformation matrix deleted. 528 1451 22 (5,16-91) INT=22 528 1451 23 (33,1-102) Taken from JENDL-3.2 covariance file. 528 1451 24 *********************************************************** 528 1451 25 09-08 Photon multiplicities were revised for MF/MT=12/102. 528 1451 26 21-11 revised by O.Iwamoto 528 1451 27 (MF8/MT16,22,28,29,32,33,102-105,107) JENDL/AD-2017 adopted 528 1451 28 (MF8/MT4) added 528 1451 29 528 1451 30 mf=1 General information 528 1451 31 mt=451 Descriptive data and dictionary 528 1451 32 528 1451 33 mf=2 Resonance parameters 528 1451 34 mt=151 Only scattering radius is given. 528 1451 35 528 1451 36 mf=3 Cross sections 528 1451 37 2200 m/sec cross sections and resonance integrals 528 1451 38 2200 m/sec res. integ. 528 1451 39 total 5.050 b - 528 1451 40 elastic 5.045 b - 528 1451 41 capture 5.075 mb 2.542 mb 528 1451 42 528 1451 43 mt=1 Total cross section 528 1451 44 Below 1 MeV, calculated with the multi-level Breit-Wigner 528 1451 45 formula and the resonance parameters taken from ref. /1/. 528 1451 46 In the range of 1 to 4 MeV, based on the R-matrix 528 1451 47 calculation which was performed by using Koehler et al.'s 528 1451 48 parameters /2/. Above 4 MeV, smooth curve was obtained by 528 1451 49 fitting to the experimental data of Auchampaugh et al./3/. 528 1451 50 ****** JENDL-3.3 **************************************** 528 1451 51 Above 14 MeV, the optical model calculations were performe 528 1451 52 using the parameter set of Glendinning et al./12/ 528 1451 53 The calculated values were normalized to the JENDL-3.2 528 1451 54 value at 14 MeV. 528 1451 55 ********************************************************** 528 1451 56 mt=2 Elastic scattering cross section 528 1451 57 Below 1 MeV based on the multi-level Breit-Wigner formula. 528 1451 58 In the range of 1 to 2.2 MeV, the R-matrix calculation was 528 1451 59 adopted. Above 2.2 MeV, the cross section was obtained by 528 1451 60 subtracting the reaction cross sections from the total 528 1451 61 cross section. 528 1451 62 mt=4 Total inelastic scattering cross section 528 1451 63 sum of mt=51-57 and 91. 528 1451 64 mt=16 (n,2n)B-10 cross section 528 1451 65 Calculated with gnash /4/. The optical potential 528 1451 66 parameters, the level density parameters and the level 528 1451 67 scheme are shown in Tables 1-3, respectively. 528 1451 68 mt=22 (n,n'alpha)Li-7 cross section 528 1451 69 Calculated with gnash. The optical potential parameters, 528 1451 70 the level density parameters and the level scheme are 528 1451 71 shown in Tables 1-3, respectively. 528 1451 72 mt=28 (n,n'p)Be-10 cross section 528 1451 73 Based on the gnash calculation. The parameters used are 528 1451 74 listed in Tables 1-3. 528 1451 75 mt=29 (n,n'2alpha)t cross section 528 1451 76 Based on (n,n't) cross section of the gnash calculation 528 1451 77 and normalized to he production cross section of Kneff 528 1451 78 et al. /5/. 528 1451 79 mt=32 (n,n'd)Be-9 cross section 528 1451 80 Based on the gnash calculation. The parameters used are 528 1451 81 listed in Tables 1-3. 528 1451 82 mt=33 (n,n't)Be-8 cross section 528 1451 83 Based on the gnash calculation. The parameters used are 528 1451 84 listed in Tables 1-3. 528 1451 85 mt=51 Inelastic scattering 528 1451 86 The R-matrix calculation with Koehler et al.'s parameters 528 1451 87 was adopted below 7 MeV. Above 7 mev, the gnash and DWBA 528 1451 88 calculations were performed. The sum of both results 528 1451 89 was adopted, and normalized to the experimental data of 528 1451 90 Koehler et al. /2/ and Glendinning et al. /6/. 528 1451 91 mt=52,53 Inelastic scattering 528 1451 92 Below 7 MeV, based on the R-matrix calculation with 528 1451 93 the searched parameters. Above 7 MeV, the sum of the gnash 528 1451 94 and DWBA calculations was adopted, and fitted to the 528 1451 95 experimental data of Glendinning et al.. 528 1451 96 mt=54-57 Inelastic scattering 528 1451 97 The sum of results of the gnash and DWBA calculations was 528 1451 98 normalized to be the result of Oktavian's ddx data /7/. 528 1451 99 mt=91 Continuum inelastic scattering 528 1451 100 Above 7.2 MeV, continuum levels were adopted. 528 1451 101 Based on the gnash calculation. 528 1451 102 mt=102 Capture cross section 528 1451 103 Calculated from the multi-level Breit-Wigner formula. 528 1451 104 The direct capture /1/ is also considered. 528 1451 105 mt=103 (n,p)Be-11 cross section 528 1451 106 Based on the gnash calculation with being normalized to 528 1451 107 the experimental data of Stepancic et al. /8/. The 528 1451 108 parameters used are shown in Tables 1-3, respectively. 528 1451 109 mt=104 (n,d)Be-10 cross section 528 1451 110 Based on the gnash calculation. 528 1451 111 mt=105 (n,t)Be-9 cross section 528 1451 112 Based on the gnash calculation. 528 1451 113 mt=107 (n,alpha)Li-8 cross section 528 1451 114 The gnash calculation was performed, and normalized to the 528 1451 115 experimental data of Antolkovic et al. /9/ and 528 1451 116 Scobel et al. /10/. The parameters used are shown in 528 1451 117 Tables 1-3, respectively. 528 1451 118 528 1451 119 mf=4 Angular distributions of secondary neutrons 528 1451 120 mt=2 528 1451 121 The R-matrix and DWBA calculations were adopted below 528 1451 122 8 MeV and above 8 MeV, respectively. 528 1451 123 mt=16,22,28,29,32,33,91 528 1451 124 Assumed to be isotropic in the center of mass system. 528 1451 125 mt=51,52,53 528 1451 126 Below 8 MeV based on R-matrix calculation. Above 8 MeV, 528 1451 127 based on the DWBA and the gnash calculations. 528 1451 128 mt=54,55,56,57 528 1451 129 Based on the DWBA and the gnash calculations. 528 1451 130 528 1451 131 mf=5 Energy distributions of secondary neutrons 528 1451 132 mt=16,22,28,29,32,33,91 528 1451 133 Based on the gnash calculation. 528 1451 134 528 1451 135 mf=12-15 Gamma-ray data 528 1451 136 Based on the gnash calculation. 528 1451 137 528 1451 138 mf=33 Covariances of cross sections (ref. 19) 528 1451 139 mt=1 528 1451 140 Based on experimental data. A chi-value was 6.212. 528 1451 141 mt=2 528 1451 142 Constructed from mt=1 and 102. 528 1451 143 mt=102 528 1451 144 Based on experimental data. A chi-value was 1.406. 528 1451 145 528 1451 146 Table 1 The optical potential parameters 528 1451 147 ------------------------------------------------------------------ 528 1451 148 neutron V = 41.8-0.005E MeV* r0= 1.40 fm a0= 0.35 fm ref.12 528 1451 149 Ws= 1.01E MeV* ri= 1.15 fm* ai= 0.50 fm 528 1451 150 528 1451 151 proton V = 66.1-0.273E MeV r0= 1.15 fm a0= 0.57 fm ref.13 528 1451 152 Ws= 1.50+0.581E MeV ri= 1.15 fm ai= 0.5 fm 528 1451 153 Vsym = 5.5 MeV r0= 1.15 fm a0= 0.57 fm 528 1451 154 528 1451 155 deuteron V = 80.0 MeV* r0= 1.0 fm* a0= 1.0 fm* ref.14 528 1451 156 Wv= 30.0 MeV ri= 1.0 fm* ai= 0.8 fm* 528 1451 157 Vsym = 6.0 MeV* r0= 1.0 fm* a0= 1.0 fm* 528 1451 158 528 1451 159 triton V = 103.0+20.0E MeV* r0= 0.85 fm a0= 0.70 fm ref.15 528 1451 160 Wv= 1.49E MeV* ri= 2.06 fm ai= 0.72 fm 528 1451 161 Vsym = 8.55 MeV* r0= 0.85 fm a0= 0.70 fm 528 1451 162 528 1451 163 alpha V = 285.2-2.40E MeV* r0= 1.61 fm* a0= 0.55 fm* ref.16 528 1451 164 Ws= 16.16-0.70E MeV* ri= 1.81 fm ai= 0.65 fm 528 1451 165 ------------------------------------------------------------------ 528 1451 166 note : E is incident neutron energy in lab. system. 528 1451 167 * means that parameter is modified from original one. 528 1451 168 528 1451 169 Table 2 The level density parameters 528 1451 170 --------------------------------------------------------- 528 1451 171 a(1/MeV) t(MeV) pair.(MeV) 528 1451 172 --------------------------------------------------------- 528 1451 173 B-10 1.196 7.990 0.0 528 1451 174 B-11 1.431 6.112 2.67 528 1451 175 B-12 1.491 6.201 0.0 528 1451 176 Be-8 1.115 9.187 5.13 528 1451 177 Be-9 1.125 8.248 2.46 528 1451 178 Be-10 1.088 10.029 5.13 528 1451 179 Be-11 1.419 7.277 2.46 528 1451 180 Li-7 1.138 7.197 2.67 528 1451 181 Li-8 1.115 8.170 0.0 528 1451 182 --------------------------------------------------------- 528 1451 183 528 1451 184 Table 3 The level scheme (energy(MeV), spin and parity) /17-18/ 528 1451 185 ------------------------------------------------------------------ 528 1451 186 B-10 B-11 Be-10 Be-11 Li-7 Li-8 528 1451 187 ------------------------------------------------------------------ 528 1451 188 gs 0.0 3+ 0.0 3/2- 0.0 0+ 0.0 1/2+ 0.0 3/2- 0.0 2+ 528 1451 189 1 0.718 1+ 2.125 1/2- 3.368 2+ 0.320 1/2- 0.478 1/2- 0.981 1+ 528 1451 190 2 1.740 0+ 4.445 5/2- 5.958 2+ 4.630 7/2- 528 1451 191 3 2.154 1+ 5.020 3/2- 5.960 1- 6.680 5/2- 528 1451 192 4 3.587 2+ 6.743 7/2- 6.179 0+ 7.460 5/2- 528 1451 193 5 4.774 3+ 6.792 1/2+ 6.263 2- 9.670 7/2- 528 1451 194 6 5.110 2- 9.120 7/2+ 7.371 3- 9.850 3/2- 528 1451 195 7 5.164 2+ 10.60 7/2+ 7.452 2+ 11.240 3/2- 528 1451 196 8 5.180 1+ 9.270 4- 528 1451 197 9 5.926 2+ 9.400 2+ 528 1451 198 10 6.025 4+ 528 1451 199 11 6.127 3- 528 1451 200 12 6.561 4- 528 1451 201 13 6.873 1- 528 1451 202 14 7.002 2+ 528 1451 203 15 7.430 2- 528 1451 204 16 7.467 1+ 528 1451 205 17 7.479 2+ 528 1451 206 18 7.561 0+ 528 1451 207 19 7.670 1+ 528 1451 208 20 7.819 1- 528 1451 209 21 8.070 2+ 528 1451 210 22 8.700 2+ 528 1451 211 23 8.889 3- 528 1451 212 24 8.895 2+ 528 1451 213 ------------------------------------------------------------------ 528 1451 214 528 1451 215 References 528 1451 216 1) Mughabghab S.F. et al. : 'Neutron Cross Sections' Vol.1 528 1451 217 Part A (academic press 1981, new york) 528 1451 218 2) Koehler P.E. et al.: Nucl. Phys. A394 (1983) 221 528 1451 219 3) Auchampaugh G.F. et al.: Nucl. Sci. Eng. 69 (1979) 30 528 1451 220 4) Young P.G. et al.: GNASH, a preequilibrium,statistical 528 1451 221 nuclear-model code for calculation of cross section and 528 1451 222 emission spectra, LA-6947 (1977). 528 1451 223 5) Kneff D.W. et al.: Nucl. Sci. Eng. 92 (1986) 491 528 1451 224 6) Glendinning S.G. et al.: Bull. Am. Phys. Soc. 24 (1979) 656 528 1451 225 7) Takahashi A. et al.: INDC(JPN)-103/L (1986) 528 1451 226 8) Stepancic B.Z. et al.: Bull. Inst. Boris Kidric 17 (1966) 237 528 1451 227 9) Antolkovic B. et al.: Nucl. Phys. A325 (1979) 189 528 1451 228 10) Scobel W. et al.: Zeitschrift f. Naturforschung, Section A 528 1451 229 25 (1970) 1406 528 1451 230 11) Cookson J.A. et al.: Nucl. Phys. A146 (1970) 417 528 1451 231 12) Glendinning S.G. et al.: Nucl. Sci. Eng. 80 (1982) 256 528 1451 232 13) Watson B.A. et al.: Phys. Rev. 182 (1969) 977 528 1451 233 14) Miljanic D. et al.: Nucl. Phys. A176 (1971) 110 528 1451 234 15) Herling G.H. et al.: Phys. Rev. 178 (1969) 178 528 1451 235 16) Matsuki S. et al.: J. Phys. Soc. Japan 26 (1969) 1344 528 1451 236 17) Ajzenberg-Selove F. : Nucl. Phys. A413 (1984) 1 528 1451 237 18) Ajzenberg-Selove F. : ibid. A433 (1985) 1 528 1451 238 19) Shibata K. et al.: JAERI-Research 98-045 (1998). 528 1451 239 528 1451 240 1 451 266 1 528 1451 241 2 151 4 1 528 1451 242 3 4 44 1 528 1451 243 3 16 7 1 528 1451 244 3 22 7 1 528 1451 245 3 28 7 1 528 1451 246 3 29 7 1 528 1451 247 3 32 5 1 528 1451 248 3 33 7 1 528 1451 249 3 102 306 1 528 1451 250 3 103 7 1 528 1451 251 3 104 8 1 528 1451 252 3 105 8 1 528 1451 253 3 107 8 1 528 1451 254 8 4 2 1 528 1451 255 8 16 2 1 528 1451 256 8 22 2 1 528 1451 257 8 28 2 1 528 1451 258 8 29 2 1 528 1451 259 8 32 2 1 528 1451 260 8 33 2 1 528 1451 261 8 102 2 1 528 1451 262 8 103 2 1 528 1451 263 8 104 2 1 528 1451 264 8 105 2 1 528 1451 265 8 107 2 1 528 1451 266 528 1 099999 528 0 0 0 5.011000+3 1.091470+1 0 0 1 0 528 2151 1 5.011000+3 1.000000+0 0 0 1 0 528 2151 2 1.000000-5 2.000000+7 0 0 0 0 528 2151 3 1.500000+0 5.000000-1 0 0 0 0 528 2151 4 528 2 099999 528 0 0 0 5.011000+3 1.091470+1 0 0 0 0 528 3 4 1 0.000000+0-2.125000+6 0 0 1 123 528 3 4 2 123 2 528 3 4 3 2.319700+6 0.000000+0 2.319800+6 4.843330-5 2.319900+6 9.686670-5 528 3 4 4 2.320000+6 1.453000-4 2.340000+6 3.329900-4 2.360000+6 4.796200-4 528 3 4 5 2.380000+6 6.262100-4 2.400000+6 7.878300-4 2.420000+6 9.800300-4 528 3 4 6 2.440000+6 1.227700-3 2.460000+6 1.580100-3 2.480000+6 2.150900-3 528 3 4 7 2.500000+6 3.245600-3 2.520000+6 5.848700-3 2.540000+6 1.357700-2 528 3 4 8 2.560000+6 3.017400-2 2.580000+6 2.399400-2 2.600000+6 1.391400-2 528 3 4 9 2.620000+6 9.891800-3 2.640000+6 8.293500-3 2.670000+6 7.580700-3 528 3 4 10 2.700000+6 7.719800-3 2.733000+6 8.353800-3 2.767000+6 9.323800-3 528 3 4 11 2.800000+6 1.045900-2 2.833000+6 1.169000-2 2.867000+6 1.295500-2 528 3 4 12 2.900000+6 1.408300-2 2.933000+6 1.503400-2 2.967000+6 1.578500-2 528 3 4 13 3.000000+6 1.629600-2 3.033000+6 1.663800-2 3.067000+6 1.688600-2 528 3 4 14 3.100000+6 1.710700-2 3.133000+6 1.739200-2 3.167000+6 1.784100-2 528 3 4 15 3.200000+6 1.851500-2 3.233000+6 1.952500-2 3.267000+6 2.104700-2 528 3 4 16 3.300000+6 2.316300-2 3.333000+6 2.612800-2 3.367000+6 3.036300-2 528 3 4 17 3.400000+6 3.590900-2 3.433000+6 4.296900-2 3.467000+6 5.124900-2 528 3 4 18 3.500000+6 5.845800-2 3.533000+6 6.216500-2 3.567000+6 6.075600-2 528 3 4 19 3.600000+6 5.557000-2 3.633000+6 4.915700-2 3.667000+6 4.316700-2 528 3 4 20 3.700000+6 3.867500-2 3.750000+6 3.447400-2 3.800000+6 3.300300-2 528 3 4 21 3.850000+6 3.382900-2 3.900000+6 3.646700-2 3.950000+6 3.972700-2 528 3 4 22 4.000000+6 4.146500-2 4.000000+6 4.241300-2 4.050000+6 4.478800-2 528 3 4 23 4.100000+6 4.762400-2 4.150000+6 5.126500-2 4.200000+6 5.599600-2 528 3 4 24 4.250000+6 6.205600-2 4.300000+6 6.968600-2 4.350000+6 7.916200-2 528 3 4 25 4.400000+6 9.074700-2 4.450000+6 1.045900-1 4.500000+6 1.204700-1 528 3 4 26 4.550000+6 1.375200-1 4.600000+6 1.539400-1 4.650000+6 1.673200-1 528 3 4 27 4.700000+6 1.757200-1 4.750000+6 1.786800-1 4.800000+6 1.774000-1 528 3 4 28 4.850000+6 1.738500-1 4.852250+6 1.736790-1 4.900000+6 1.778780-1 528 3 4 29 4.950000+6 1.838040-1 5.000000+6 1.926710-1 5.050000+6 2.054370-1 528 3 4 30 5.100000+6 2.220030-1 5.150000+6 2.402800-1 5.200000+6 2.555460-1 528 3 4 31 5.250000+6 2.624420-1 5.300000+6 2.585590-1 5.479900+6 2.742960-1 528 3 4 32 5.479930+6 2.742980-1 5.500000+6 2.758890-1 5.609940+6 2.896950-1 528 3 4 33 5.739960+6 3.058810-1 6.000000+6 3.378560-1 6.500000+6 3.536570-1 528 3 4 34 7.000000+6 3.684670-1 7.360790+6 3.724320-1 7.360800+6 3.724320-1 528 3 4 35 7.414280+6 3.728990-1 7.414300+6 3.729000-1 7.707140+6 3.809280-1 528 3 4 36 7.707150+6 3.809280-1 7.859660+6 3.847570-1 8.000000+6 4.000800-1 528 3 4 37 8.000000+6 4.000800-1 9.000000+6 4.681320-1 1.000000+7 4.910530-1 528 3 4 38 1.003200+7 4.903320-1 1.027400+7 4.893130-1 1.051600+7 4.880920-1 528 3 4 39 1.100000+7 4.850840-1 1.157100+7 4.584780-1 1.157120+7 4.584690-1 528 3 4 40 1.200000+7 4.377960-1 1.300000+7 3.737800-1 1.400000+7 2.982830-1 528 3 4 41 1.500000+7 2.401620-1 1.570000+7 1.924840-1 1.600000+7 1.726620-1 528 3 4 42 1.630000+7 1.594380-1 1.700000+7 1.329430-1 1.800000+7 9.543680-2 528 3 4 43 1.900000+7 7.468530-2 1.900000+7 7.468530-2 2.000000+7 5.988280-2 528 3 4 44 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 16 1 -1.145600+7-1.145600+7 0 0 1 10 528 3 16 2 10 2 528 3 16 3 1.250560+7 0.000000+0 1.300000+7 5.721330-5 1.400000+7 1.414440-3 528 3 16 4 1.500000+7 7.584970-3 1.570000+7 1.296210-2 1.630000+7 1.767060-2 528 3 16 5 1.700000+7 2.060570-2 1.800000+7 2.491940-2 1.900000+7 2.818320-2 528 3 16 6 2.000000+7 3.091690-2 528 3 16 7 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 22 1 -8.665580+6-8.665580+6 0 0 1 12 528 3 22 2 12 2 528 3 22 3 9.459530+6 0.000000+0 1.000000+7 7.119900-4 1.100000+7 6.357890-3 528 3 22 4 1.200000+7 3.282590-2 1.300000+7 6.747230-2 1.400000+7 1.010020-1 528 3 22 5 1.500000+7 1.360000-1 1.600000+7 1.670000-1 1.700000+7 1.951790-1 528 3 22 6 1.800000+7 2.143820-1 1.900000+7 2.222580-1 2.000000+7 2.232850-1 528 3 22 7 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 28 1 -1.122940+7-1.122940+7 0 0 1 10 528 3 28 2 10 2 528 3 28 3 1.225820+7 0.000000+0 1.300000+7 1.129560-4 1.400000+7 1.104490-3 528 3 28 4 1.500000+7 3.114510-3 1.570000+7 4.315120-3 1.630000+7 5.468120-3 528 3 28 5 1.700000+7 6.655560-3 1.800000+7 8.601730-3 1.900000+7 1.019920-2 528 3 28 6 2.000000+7 1.177280-2 528 3 28 7 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 29 1 -1.113190+7-1.113190+7 0 0 1 10 528 3 29 2 10 2 528 3 29 3 1.215180+7 0.000000+0 1.290000+7 2.951580-4 1.390000+7 1.494840-2 528 3 29 4 1.490000+7 4.501500-2 1.560000+7 7.924700-2 1.620000+7 1.058330-1 528 3 29 5 1.690000+7 1.255840-1 1.790000+7 1.843280-1 1.890000+7 2.334700-1 528 3 29 6 2.000000+7 2.744060-1 528 3 29 7 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 32 1 -1.581680+7-1.581680+7 0 0 1 4 528 3 32 2 4 2 528 3 32 3 1.726590+7 0.000000+0 1.800000+7 4.153470-5 1.900000+7 9.705240-4 528 3 32 4 2.000000+7 2.984150-3 528 3 32 5 528 3 099999 5.011000+3 1.091470+1 0 0 0 0 528 3 33 1 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