JENDL-5 (Neutron sublibrary (activation cs)) Be- 9 0 0 0 0 4.009000+3 8.934760+0 0 0 6 1 425 1451 1 0.000000+0 0.000000+0 0 0 0 6 425 1451 2 1.000000+0 2.000000+7 0 0 10 5 425 1451 3 2.936000+2 0.000000+0 4 0 226 14 425 1451 4 4-Be- 9 JAEA Eval-Feb09 K.Shibata 425 1451 5 JAERI-M 84-226 DIST-DEC21 20100217 425 1451 6 ----JENDL-5 MATERIAL 425 425 1451 7 -----INCIDENT NEUTRON DATA 425 1451 8 ------ENDF-6 FORMAT 425 1451 9 425 1451 10 HISTORY 425 1451 11 84-08 Reevaluated for JENDL-3 by K.Shibata. 425 1451 12 Details of the evaluation are given in ref/1/. 425 1451 13 89-01 Modified by considering neutron emission spectra 425 1451 14 94-02 Evaluated for JENDL Fusion File. 425 1451 15 Neutron and alpha emission spectra from the (n,2n) 425 1451 16 reaction were calculated and given in MF6. 425 1451 17 Elastic angular distributios were modified by taking 425 1451 18 account of new measurements. 425 1451 19 99-07 DDX above 15 MeV were modified by considering the 425 1451 20 measurements /45/. 425 1451 21 01-09 Compiled by K.Shibata for JENDL-3.3. 425 1451 22 The library was taken from JENDL fusion file. 425 1451 23 ** modified parts for JENDL-3.3 (change from JENDL FF)**** 425 1451 24 (1,451) Updated. 425 1451 25 (3,251) Deleted. 425 1451 26 (6,16) Above 15 MeV. 425 1451 27 (4,2) Transformation matrix deleted. 425 1451 28 ********************************************************** 425 1451 29 10-02 Re-evaluated by K.Shibata for JENDL-4. 425 1451 30 *** Modified parts for JENDL-4 *************************** 425 1451 31 (1,451) Updated 425 1451 32 (3,1) Modified 425 1451 33 (3,2) Re-calculated 425 1451 34 (3,16) Revised near the threshold 425 1451 35 (3,102) Thermal cross section was updated. 425 1451 36 ********************************************************** 425 1451 37 21-11 revised by O.Iwamoto 425 1451 38 (MF8/MT16,102-105,107) JENDL/AD-2017 adopted 425 1451 39 425 1451 40 MF=1 General Information 425 1451 41 MT=451 Descriptive data 425 1451 42 425 1451 43 MF=2 Resonance Parameter 425 1451 44 MT=151 Scattering radius only. 425 1451 45 425 1451 46 MF=3 Cross Sections 425 1451 47 Thermal cross sections and resonance integrals at 300 K 425 1451 48 ---------------------------------------------------------- 425 1451 49 0.0253 eV res. integ. (*) 425 1451 50 (barns) (barns) 425 1451 51 ---------------------------------------------------------- 425 1451 52 Total 6.5119E+00 425 1451 53 Elastic 6.5027E+00 425 1451 54 n,gamma 8.4909E-03 3.8223E-03 425 1451 55 ---------------------------------------------------------- 425 1451 56 (*) Integrated from 0.5 eV to 10 MeV. 425 1451 57 425 1451 58 MT=1 Sig-t 425 1451 59 Below 1 eV, sum of sig-el and sig-cap. Between 1 eV and 425 1451 60 830 keV, the cross section was calculated on the basis of 425 1451 61 the R-matrix theory. The R-matrix parameters were 425 1451 62 obtained so as to give the best fit to the experimental 425 1451 63 data /2/-/6/. Above 830 keV, based on the measurements 425 1451 64 /5/,/7/,/8/. 425 1451 65 ***** For JENDL-4 *************************************** 425 1451 66 In the energy region from 80 keV to 890 keV, the cross 425 1451 67 sections were reduced by considering those of JENDL-2 425 1451 68 and the latest experimental data./46/ 425 1451 69 ********************************************************** 425 1451 70 MT=2 Sig-el 425 1451 71 Below 1 eV, sig-el = 6.151 barns. 425 1451 72 Above 1 ev, the cross section was obtained by subtracting 425 1451 73 the reaction cross section from the total cross section. 425 1451 74 MT=3 Non-elastic 425 1451 75 Sum of MT=16,102,104,103,105,107 425 1451 76 MT=16 425 1451 77 The cross sections were evaluated on the basis of 425 1451 78 experimental data /9/-/17/. 425 1451 79 ***** For JENDL-4 *************************************** 425 1451 80 The cross sections near the threshold were modified on the 425 1451 81 basis of the measurements/11/. 425 1451 82 ********************************************************** 425 1451 83 MT=102 Capture 425 1451 84 Thermal cross section of 8.49E-3 barn was obtained from 425 1451 85 the data measured by Conneely et al./18/ 425 1451 86 1/v curve was assumed over the whole energy range. 425 1451 87 MT=103 (n,p) 425 1451 88 Calculated with the statistical model. 425 1451 89 Neutron potential parameters were taken from the work 425 1451 90 of Agee and Rosen /19/: 425 1451 91 V = 49.3 - 0.33E, Ws = 5.75 , Vso = 5.5 (MeV) 425 1451 92 r = 1.25 , rs = 1.25 , rso = 1.25 (fm) 425 1451 93 a = 0.65 , b = 0.70 , aso = 0.65 (fm) 425 1451 94 Proton potential parameters are the following /20/: 425 1451 95 V = 59.5 - 0.36e, Ws = 12.0 + 0.07E, Vso = 4.9 (MeV) 425 1451 96 r = 1.24 , rs = 1.36 , rso = 1.2 (fm) 425 1451 97 rc= 1.3 (fm) 425 1451 98 a = 0.63 , b = 0.35 , aso = 0.31 (fm) 425 1451 99 The cross section was normalized to the experimental data 425 1451 100 of Augustson and Menlove /21/, who measured delayed 425 1451 101 neutros, by taking account of the branching ratio 425 1451 102 of 49.5% for Li-9 => Be-9* => 2a + n. 425 1451 103 MT=104 (n,d) 425 1451 104 Based on the experimental data of Scobel /22/. 425 1451 105 MT=105 (n,t) 425 1451 106 Based on experimental data /23/-/27/. 425 1451 107 MT=107 (n,a0) 425 1451 108 Based on the experimental data /28/-/33/. 425 1451 109 MT=251 Mu-bar 425 1451 110 Calculated from the data in file4. 425 1451 111 MT=700 (n,t0) 425 1451 112 Calculated with the statistical model. 425 1451 113 Triton potential parameters are the following /34/: 425 1451 114 V = 140.0 , Ws = 7.5 , Vso = 6.0 (MeV) 425 1451 115 r = 1.20 , rs = 2.69 , rso = 1.20 , rc = 1.30 (fm) 425 1451 116 a = 0.45 , b = 0.36 , aso = 0.7 (fm) 425 1451 117 Normalization was taken so that the total (n,t) cross 425 1451 118 section might be consistent with experimental data. 425 1451 119 MT=701 (n,t1) 425 1451 120 Total (n,t) - (n,t1) 425 1451 121 425 1451 122 425 1451 123 MF=4 Angular Distributions 425 1451 124 MT=2 425 1451 125 1.0E-5 eV to 50 keV Isotropic in CM. 425 1451 126 50 keV to 17 MeV Based on the experimental data 425 1451 127 /35/-/42/. 425 1451 128 18 MeV to 20 MeV Optical-model calculations using 425 1451 129 the potential parameters of 425 1451 130 Agee and Rosen /19/. 425 1451 131 MF=6 Double Differential Cross Sections 425 1451 132 MT=16 425 1451 133 Calculated by taking account of kinematics of 425 1451 134 possible reactions. The following reactions were 425 1451 135 taken into account: 425 1451 136 n + Be-9 -> 2n + Be-8 -> 2n + 2a 425 1451 137 -> He-5 + He-5 -> 2n + 2a 425 1451 138 -> a + He-6(1.8) -> 2n + 2a 425 1451 139 -> n + Be-9(2.4) -> 2n + Be-8 -> 2n + 2a 425 1451 140 -> n + Be-9(4.7) -> 2n + Be-8 -> 2n + 2a 425 1451 141 -> n + a + He-5 -> 2n + 2a 425 1451 142 -> n + Be-9(6.8) -> 2n + Be-8 -> 2n + 2a 425 1451 143 -> n + a + He-5 -> 2n + 2a 425 1451 144 -> n + Be-9(7.9) -> 2n + Be-8 -> 2n + 2a 425 1451 145 -> n + a + He-5 -> 2n + 2a 425 1451 146 -> n + Be-9(11.28) -> 2n + Be-8 -> 2n + 2a 425 1451 147 -> n + a + He-5 -> 2n + 2a 425 1451 148 -> n + Be-9(11.81) -> 2n + Be-8 -> 2n + 2a 425 1451 149 -> n + a + He-5 -> 2n + 2a 425 1451 150 -> n + Be-9(13.79) -> 2n + Be-8 -> 2n + 2a 425 1451 151 -> n + a + He-5 -> 2n + 2a 425 1451 152 -> n + Be-9(cont.) -> 2n + Be-8 -> 2n + 2a 425 1451 153 -> n + a + He-5 -> 2n + 2a 425 1451 154 The branching ratio of each reaction was determined on 425 1451 155 the basis of experimental data and of statistical model 425 1451 156 calculations. 425 1451 157 MT=600 425 1451 158 Isotropic angular distribution assumed. 425 1451 159 MT=650 425 1451 160 Isotropic angular distribution assumed. 425 1451 161 MT=700 425 1451 162 Isotropic angular distribution assumed. 425 1451 163 MT=701 425 1451 164 Isotropic angular distribution assumed. 425 1451 165 MT=800 425 1451 166 Angular distributions were obtained from the work of 425 1451 167 Smolec et al./43/ 425 1451 168 425 1451 169 MF=12 Photon-Production Multiplicities 425 1451 170 MT=102 425 1451 171 Based on the measurements of Jurney /44/. 425 1451 172 425 1451 173 MF=14 Photon Angular Distributions 425 1451 174 MT=102 425 1451 175 Assumed to be isotropic. 425 1451 176 425 1451 177 References 425 1451 178 1) Shibata, K.: JAERI-M 84-226 (1984). 425 1451 179 2) Bockelman, C.K.: Phys. Rev. 80 (1950) 1011. 425 1451 180 3) Hibdon, C.T. and Langsdorf, Jr., A.: Phys. Rev. 98 (1955) 223. 425 1451 181 4) Bilpuch, E.G. et al.: Taken from EXFOR (1962). 425 1451 182 5) Schwartz, R.B. et al.: Bull. Am. Phys. Soc. 16 (1971) 495. 425 1451 183 6) Cabe, J and Cance, M.: CEA-R-4524 (1973). 425 1451 184 7) Foster, Jr. D.G. and Glasgow, D.W.: Phys. Rev. C3 (1971) 576. 425 1451 185 8) Auchampaugh, G.F. et al.: Nucl. Sci. Eng. 69 (1979) 30. 425 1451 186 9) Ashby, V.J. et al.: Phys. Rev. 111 (1958) 616. 425 1451 187 10) Catron, H.C. et al.: Phys. Rev. 123 (1961) 218. 425 1451 188 11) Holmberg, M. and Hansen, J.: Nucl. Phys. A129 (1969) 305. 425 1451 189 12) Bloser, M: Atomkernenergie 20 (1972) 309. 425 1451 190 13) Drake, D.M. et al.: Nucl. Sci. Eng. 63 (1977) 401. 425 1451 191 14) Auchampaugh G.F. et al.: Proc. Symp. Neutron Cross Sections 425 1451 192 from 10 to 40 MeV, BNL, 1977, p.231. 425 1451 193 15) Baba, M. et al.: Proc. Int. Conf. Neutron Physics and Nuclear 425 1451 194 Data for Reactors and Other Applied Purposes, Harwell 1978, 425 1451 195 (1979), p.198. 425 1451 196 16) Takahasi, A. et al.: Proc. Int. Conf. Nuclear Data for 425 1451 197 Science and Technology, Mito, 1988, p.205 (1988). 425 1451 198 17) Baba, M et al.: ibid., p.209 (1988). 425 1451 199 18) Conneely, C.M. et al.: Nucl. Instrum. Meth., A248 (1986) 426. 425 1451 200 19) Agee, F.P. and Rosen, L.: LA-3538-MS (1966). 425 1451 201 20) Votava, H.J. et al.: Nucl. Phys. A204 (1973) 529. 425 1451 202 21) Augustson, R.H. and Menlove, H.O.: Nucl. Sci. Eng. 54(1974)190 425 1451 203 22) Scobel, W.: Z. Naturforsch. A24 (1969) 1858. 425 1451 204 23) Wyman, M.E et al.: Phys. Rev. 112 (1958) 1264. 425 1451 205 24) Biro, T. et al.: J. Inorg. Nucl. Chem. 37 (1975) 1583. 425 1451 206 25) Body, Z.T. et al.: Proc. Int. Conf. Nuclear Data for 425 1451 207 Science and Technology, Antwerp, 1982, p.368 (1982). 425 1451 208 26) Liskien, H. et al.: Nucl. Sci. Eng. 98 (1988) 266. 425 1451 209 27) Woelfle, R. et al.: Radiochimica Acta 50 (1990) 5. 425 1451 210 28) Shibata, K. and Shirato, S.: J. Phys. Soc. Jpn. 52 (1983) 3748 425 1451 211 29) Perroud, J.P. and Sellem, Ch.: Nucl. Phys. A227 (1974) 330. 425 1451 212 30) Battat, M.E. and Ribe, F.L.: Nucl. Phys. 89 (1953) 80. 425 1451 213 31) Stelson, P.H. and Campbell, E.C.: Nucl. Phys. 106 (1957) 1252. 425 1451 214 32) Bass, R. et al.: Nucl. Phys. 23 (1961) 122. 425 1451 215 33) Paic, G. et al.: Nucl. Phys. A96 (1967) 476. 425 1451 216 34) Luedecke, H. et al.: Nucl. Phys. A109 (1968) 676. 425 1451 217 35) Marion, J.B. et al.: Phys. Rev. 114 (1959) 1584. 425 1451 218 36) Levin, J.S. and Cranberg, L.: Taken from EXFOR (1960). 425 1451 219 37) Phillips, D.D.: Taken from EXFOR (1961). 425 1451 220 38) Lane, R.O. et al.: Ann. Phys. 12 (1961) 135. 425 1451 221 39) Lane, R.O. et al.: Phys. Rev. 133B (1964) 409. 425 1451 222 40) Hogue , H.H. et al.: Nucl. Sci. Eng. 68 (1978) 38. 425 1451 223 41) Sugimoto, M. et al.: Nucl. Sci. Eng. 103 (1989) 37. 425 1451 224 42) Templon, J.A., et al.: Nucl. Sci. Eng. 91 (1985) 451. 425 1451 225 43) Smolec, W. et al.: Nucl. Phys. A257 (1976) 397. 425 1451 226 44) Jurney, E.T.: Proc. Third Symp. Neutron Capture Gamma Rays, 425 1451 227 BNL 1978, (1979), p.46. 425 1451 228 45) Ibaraki, M., et al.: J. Nucl. Sci. Technol., 35, 843 (1998). 425 1451 229 46) Danon, Y., et al.: Nucl. Sci. Eng., 161, 321 (2009). 425 1451 230 1 451 244 1 425 1451 231 2 151 4 1 425 1451 232 3 16 35 1 425 1451 233 3 102 121 1 425 1451 234 3 103 6 1 425 1451 235 3 104 10 1 425 1451 236 3 105 8 1 425 1451 237 3 107 26 1 425 1451 238 8 16 2 1 425 1451 239 8 102 2 1 425 1451 240 8 103 2 1 425 1451 241 8 104 2 1 425 1451 242 8 105 2 1 425 1451 243 8 107 2 1 425 1451 244 425 1 099999 425 0 0 0 4.009000+3 8.934760+0 0 0 1 0 425 2151 1 4.009000+3 1.000000+0 0 0 1 0 425 2151 2 1.000000-5 2.000000+7 0 0 0 0 425 2151 3 1.500000+0 6.900000-1 0 0 0 0 425 2151 4 425 2 099999 425 0 0 0 4.009000+3 8.934760+0 0 0 0 0 425 3 16 1 -1.573310+6-1.573310+6 0 0 1 95 425 3 16 2 95 2 425 3 16 3 1.749400+6 0.000000+0 1.868030+6 0.000000+0 1.868250+6 8.980580-7 425 3 16 4 1.868480+6 1.859970-6 1.868930+6 3.810070-6 1.869840+6 8.028860-6 425 3 16 5 1.870750+6 1.261580-5 1.871660+6 1.757060-5 1.873480+6 2.858290-5 425 3 16 6 1.875300+6 4.106340-5 1.877120+6 5.501020-5 1.878950+6 7.050970-5 425 3 16 7 1.882600+6 1.058360-4 1.886260+6 1.471460-4 1.889930+6 1.944710-4 425 3 16 8 1.893610+6 2.478420-4 1.897290+6 3.071200-4 1.904680+6 4.439360-4 425 3 16 9 1.912090+6 6.048370-4 1.919530+6 7.901410-4 1.927000+6 9.999990-4 425 3 16 10 1.927000+6 9.999990-4 1.963500+6 1.500000-3 2.000000+6 2.000000-3 425 3 16 11 2.024850+6 2.968800-3 2.050000+6 4.000000-3 2.100000+6 6.000000-3 425 3 16 12 2.149420+6 7.905170-3 2.200000+6 1.000000-2 2.300000+6 1.400000-2 425 3 16 13 2.400000+6 1.800000-2 2.500000+6 2.200000-2 2.600000+6 2.600000-2 425 3 16 14 2.620000+6 2.700000-2 2.700000+6 3.300000-2 2.800000+6 2.000000-1 425 3 16 15 2.900000+6 2.700000-1 3.100000+6 3.700000-1 3.200000+6 4.079990-1 425 3 16 16 3.402480+6 4.410720-1 3.426600+6 4.453950-1 3.450900+6 4.494920-1 425 3 16 17 3.500000+6 4.569990-1 3.548960+6 4.633140-1 3.598610+6 4.687930-1 425 3 16 18 3.700000+6 4.760020-1 3.847080+6 4.936500-1 4.000000+6 5.050010-1 425 3 16 19 4.057000+6 5.080010-1 4.175000+6 5.129980-1 4.329000+6 5.210000-1 425 3 16 20 4.471000+6 5.279980-1 4.500000+6 5.289980-1 5.000000+6 5.530010-1 425 3 16 21 5.226040+6 5.566150-1 5.361270+6 5.589610-1 5.500000+6 5.609990-1 425 3 16 22 5.744560+6 5.654050-1 6.000000+6 5.689980-1 6.500000+6 5.700020-1 425 3 16 23 7.000000+6 5.719980-1 7.500000+6 5.730000-1 7.561070+6 5.731210-1 425 3 16 24 7.668490+6 5.737510-1 7.777440+6 5.741120-1 8.000000+6 5.740010-1 425 3 16 25 8.500000+6 5.661650-1 9.000000+6 5.585990-1 9.500000+6 5.503960-1 425 3 16 26 1.000000+7 5.424500-1 1.100000+7 5.258590-1 1.160000+7 5.150990-1 425 3 16 27 1.200000+7 5.086590-1 1.213000+7 5.071810-1 1.254250+7 5.011240-1 425 3 16 28 1.300000+7 4.958510-1 1.313180+7 4.940360-1 1.375000+7 4.869610-1 425 3 16 29 1.400000+7 4.838030-1 1.410000+7 4.825710-1 1.426000+7 4.802360-1 425 3 16 30 1.450000+7 4.758280-1 1.500000+7 4.678940-1 1.550000+7 4.613670-1 425 3 16 31 1.600000+7 4.548470-1 1.600720+7 4.547550-1 1.601170+7 4.547000-1 425 3 16 32 1.629000+7 4.513550-1 1.660000+7 4.478730-1 1.685000+7 4.443460-1 425 3 16 33 1.700000+7 4.425950-1 1.730000+7 4.387900-1 1.800000+7 4.292930-1 425 3 16 34 1.900000+7 4.167650-1 2.000000+7 4.041760-1 425 3 16 35 425 3 099999 4.009000+3 8.934760+0 0 0 0 0 425 3102 1 6.812090+6 6.812090+6 0 0 1 353 425 3102 2 353 2 425 3102 3 1.000000-5 4.270427-1 1.103037-5 4.066084-1 1.216691-5 3.871518-1 425 3102 4 1.342055-5 3.686262-1 1.480336-5 3.509872-1 1.632865-5 3.341921-1 425 3102 5 1.801111-5 3.182007-1 1.986691-5 3.029745-1 2.191394-5 2.884769-1 425 3102 6 2.417189-5 2.746731-1 2.666248-5 2.615297-1 2.940971-5 2.490153-1 425 3102 7 3.243999-5 2.370997-1 3.578251-5 2.257543-1 3.946943-5 2.149517-1 425 3102 8 4.353624-5 2.046661-1 4.802208-5 1.948726-1 5.297013-5 1.855478-1 425 3102 9 5.842801-5 1.766692-1 6.444825-5 1.682154-1 7.108881-5 1.601662-1 425 3102 10 7.841358-5 1.525021-1 8.649308-5 1.452047-1 9.540506-5 1.382565-1 425 3102 11 1.052353-4 1.316408-1 1.160784-4 1.253417-1 1.280388-4 1.193440-1 425 3102 12 1.412315-4 1.136333-1 1.557836-4 1.081958-1 1.718351-4 1.030186-1 425 3102 13 1.895404-4 9.808903-2 2.090701-4 9.339538-2 2.306120-4 8.892633-2 425 3102 14 2.543736-4 8.467113-2 2.805835-4 8.061954-2 3.094939-4 7.676182-2 425 3102 15 3.413832-4 7.308870-2 3.765583-4 6.959134-2 4.153577-4 6.626134-2 425 3102 16 4.581549-4 6.309067-2 5.053618-4 6.007173-2 5.574328-4 5.719724-2 425 3102 17 6.148689-4 5.446030-2 6.782232-4 5.185433-2 7.481052-4 4.937305-2 425 3102 18 8.251877-4 4.701051-2 9.102125-4 4.476102-2 1.003998-3 4.261916-2 425 3102 19 1.107447-3 4.057980-2 1.221555-3 3.863802-2 1.347420-3 3.678916-2 425 3102 20 1.486254-3 3.502876-2 1.639393-3 3.335260-2 1.808311-3 3.175665-2 425 3102 21 1.994634-3 3.023707-2 2.200155-3 2.879020-2 2.426853-3 2.741256-2 425 3102 22 2.676908-3 2.610085-2 2.952729-3 2.485190-2 3.256969-3 2.366271-2 425 3102 23 3.592557-3 2.253043-2 3.962723-3 2.145233-2 4.371030-3 2.042582-2 425 3102 24 4.821407-3 1.944842-2 5.318191-3 1.851780-2 5.866161-3 1.763171-2 425 3102 25 6.470592-3 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