JENDL-5 (Neutron sublibrary (activation cs)) Al- 27 0 0 0 0 1.302700+4 2.675000+1 0 0 6 11325 1451 1 0.000000+0 0.000000+0 0 0 0 61325 1451 2 1.000000+0 2.000000+7 0 0 10 51325 1451 3 2.936000+2 0.000000+0 4 0 233 181325 1451 4 13-Al- 27 TIT,JAERI EVAL-MAR88 Y.HARIMA,H.KITAZAWA,T.FUKAHORI 1325 1451 5 88MITO, 473 DIST-DEC21 20090828 1325 1451 6 ----JENDL-5 MATERIAL 1325 1325 1451 7 -----INCIDENT NEUTRON DATA 1325 1451 8 ------ENDF-6 FORMAT 1325 1451 9 1325 1451 10 History 1325 1451 11 21-11 revised by O.Iwamoto 1325 1451 12 (MF8/MT16,22,28,102,103,107,111) JENDL/AD-2017 adopted 1325 1451 13 (MF8/MT4) added 1325 1451 14 (MF10/MT16,107) JENDL/AD-2017 based 1325 1451 15 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 1325 1451 16 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 1325 1451 17 1325 1451 18 =========================================================== 1325 1451 19 The data were taken from JENDL-3.3. 1325 1451 20 =========================================================== 1325 1451 21 1325 1451 22 1325 1451 23 HISTORY 1325 1451 24 88-03 Evaluation was performed for JENDL-3 by Harima, Kitazawa 1325 1451 25 (Tokyo Institute of Tech.) and Fukahori (jaeri). Details 1325 1451 26 are given in ref./1/. 1325 1451 27 88-03 Compiled by Fukahori. 1325 1451 28 93-12 JENDL-3.2. 1325 1451 29 Compiled by T.Nakagawa (ndc/jaeri) 1325 1451 30 1325 1451 31 ***** Modified parts for JENDL-3.2 ******************** 1325 1451 32 (3,2) 1325 1451 33 (3,66-91) Taken from JENDL fusion file* 1325 1451 34 (3,4), (3,51-70) Cross-section curves were smoothed. 1325 1451 35 (4,16-28), (4,91) Taken from JENDL fusion file 1325 1451 36 (5,16-91) Taken from JENDL fusion file 1325 1451 37 (12,51-70), (12,102) 1325 1451 38 *********************************************************** 1325 1451 39 1325 1451 40 -------------------------------------------------------------1325 1451 41 JENDL fusion file /2/ (as of Sep. 1993) 1325 1451 42 Evaluated by B.Yu (ciae) and S.Chiba (ndc/jaeri) 1325 1451 43 Compiled by B.Yu. 1325 1451 44 1325 1451 45 Cross sections were mainly taken from JENDL-3.1, except 1325 1451 46 for the (n,n') (mt=66 to 70) and (n,n') continuum (mt=91) 1325 1451 47 reactions which were taken from the calculation with 1325 1451 48 sincros-II/3/. Angular distributions of these levels 1325 1451 49 were taken to be equal to that of mt=66 in JENDL-3. 1325 1451 50 EDXs for mt=16, 22, 28 and 91 were replaced by the 1325 1451 51 sincros-II calculation. mf=6 were created by f15tob 1325 1451 52 program. Kumabe's systematics/4/ was used. The pre- 1325 1451 53 compound/compound ratio was taken from the sincros-II 1325 1451 54 calculation. 1325 1451 55 Optical-model, level density and other parameters used 1325 1451 56 in the sincros-II calculation are described in ref./3/. 1325 1451 57 Level schemes were determined on the basis of ENDSF/5/. 1325 1451 58 -------------------------------------------------------------1325 1451 59 1325 1451 60 00-10 Re-evaluated by K. Shibata (jaeri) for JENDL-3.3 1325 1451 61 Compiled by K. Shibata 1325 1451 62 ***** Modified parts for JENDL-3.3 ***************************1325 1451 63 (1,1451) Updated 1325 1451 64 (3,1),(3,2),(3,4) Re-calculated. 1325 1451 65 (3,16) Yamamuro's calculations /15/ 1325 1451 66 (3,61),(3,62),(3,63) DWBA calculations were added. 1325 1451 67 (3,67),(3,70) DWBA calculations were added. 1325 1451 68 (3,203),(3,207) Calcualted. 1325 1451 69 (3,251) Deleted. 1325 1451 70 (4,2) Transformation matrix deleted. 1325 1451 71 (4,16),(4,22),(4,28) Deleted. 1325 1451 72 (4,91) Deleted. 1325 1451 73 (5,16-91) Deleted. 1325 1451 74 (6,16-91) Taken from JENDL fusion file. 1325 1451 75 ***************************************************************1325 1451 76 1325 1451 77 mf=1 General information 1325 1451 78 mt=451 Descriptive data and dictionary 1325 1451 79 1325 1451 80 mf=2 Resonance parameters: 1325 1451 81 mt=151 1325 1451 82 Resolved resonances : 1.0e-5 eV - 0.21 MeV 1325 1451 83 The resonance parameters were searched, using MLBW formula/6/. 1325 1451 84 An initial guess of the parameters search was taken from ref. 1325 1451 85 /7/. 1325 1451 86 1325 1451 87 Calculated 2200-m/s cross sections and resonance integrals 1325 1451 88 2200-m/sec res. integ. 1325 1451 89 elastic 1.414 b - 1325 1451 90 capture 0.231 b 0.123 b 1325 1451 91 total 1.645 b - 1325 1451 92 1325 1451 93 mf=3 Neutron cross sections 1325 1451 94 mt=1 Total cross section 1325 1451 95 Between 0.21 and 20 MeV, the cross sections were obtained by 1325 1451 96 an eye-guide so as to follow the experimental data. 1325 1451 97 mt=2 Elastic scattering cross sections 1325 1451 98 Obtained by subtracting partial cross sections from the 1325 1451 99 total cross sections. 1325 1451 100 mt=4,51-70,91 Inelastic scattering cross sections 1325 1451 101 For JENDL-3.1, cross sections up to 17-th level were calculated1325 1451 102 with the statistical-model code casthy /8/ and the coupled- 1325 1451 103 channel model code ecis /9/ or jupitor-1 /10/, taking account 1325 1451 104 of competitive processes for neutron, proton, alpha-particle 1325 1451 105 and gamma-ray emission/1/. The following levels/11/ were 1325 1451 106 taken into account. 1325 1451 107 1325 1451 108 no. energy(MeV) spin-parity 1325 1451 109 g.s. 0.0 5/2 + 1325 1451 110 1. 0.8438 1/2 + 1325 1451 111 2. 1.0145 3/2 + 1325 1451 112 3. 2.2100 7/2 + 1325 1451 113 4. 2.7340 5/2 + 1325 1451 114 5. 2.9814 3/2 + 1325 1451 115 6. 3.0040 9/2 + 1325 1451 116 7. 3.6780 1/2 + 1325 1451 117 8. 3.9560 5/2 + 1325 1451 118 9. 4.0540 3/2 - 1325 1451 119 10. 4.4090 5/2 + 1325 1451 120 11. 4.5103 11/2 + 1325 1451 121 12. 4.5800 7/2 + 1325 1451 122 13. 4.8120 5/2 + 1325 1451 123 14. 5.1550 3/2 - 1325 1451 124 15. 5.2460 5/2 + 1325 1451 125 16. 5.4199 5/2 + 1325 1451 126 17. 5.4330 9/2 + 1325 1451 127 1325 1451 128 Continuum levels were assumed above 5.6 MeV. Level density was1325 1451 129 calculated, using the Gilbert-Cameron formula. The level- 1325 1451 130 density parameters were obtained from a cumulative plot of 1325 1451 131 observed levels/1/. 1325 1451 132 1325 1451 133 For JENDL-3.2, cross sections for mt's from 66 to 70 and conti-1325 1451 134 nuum inelastic were replaced with JENDL fusion file. These mt's1325 1451 135 correspond to the following levels. 1325 1451 136 1325 1451 137 16. 5.4199 5/2 + 1325 1451 138 17. 5.4328 5/2 + 1325 1451 139 18. 5.4384 5/2 + 1325 1451 140 19. 5.4998 7/2 + 1325 1451 141 20. 5.5507 3/2 + 1325 1451 142 Above 5.6 MeV, cross sections were summed up as the continuum 1325 1451 143 inelastic (mt=91). 1325 1451 144 1325 1451 145 Several energy points were added to mt= 4, 51-70 in order to 1325 1451 146 smooth their cross section curves. 1325 1451 147 1325 1451 148 For JENDL-3.3, the direct process was considered /16/ by DWBA 1325 1451 149 calculations for mt=61,62,63,67,70. 1325 1451 150 1325 1451 151 mt=16 (n,2n) cross sections 1325 1451 152 Re-calculated by the sincros-II code /17/. 1325 1451 153 mt=22 (n,na) cross sections 1325 1451 154 Calculated by the statistical model with the gnash code/1,12/. 1325 1451 155 optical potential for alpha-particles was determined, using 1325 1451 156 the dispersion theory /13/. 1325 1451 157 mt=28 (n,np) cross sections 1325 1451 158 Calculated by the statistical model with the gnash code/1,12/. 1325 1451 159 mt=102 capture 1325 1451 160 Calculated with the statistical-model code casthy/8/ and the 1325 1451 161 direct-semidirect-model code hikari/14/. The statistical- 1325 1451 162 model calculations were normalized to 0.6 mb at 0.6 MeV. 1325 1451 163 mt=103 (n,p) cross sections 1325 1451 164 Calculated by the statistical model with the gnash code/1,12/. 1325 1451 165 mt=107 (n,a) cross sections 1325 1451 166 Obtained by an eye-guide to follow observed values /15/. 1325 1451 167 mt=111 (n,2p) cross sections 1325 1451 168 Calculated by the statistical model with the gnash code/1,12/. 1325 1451 169 mt=203 proton production 1325 1451 170 Sum of mt=28 and 103. 1325 1451 171 mt=207 alpha production 1325 1451 172 Sum of mt=22 and 107. 1325 1451 173 1325 1451 174 mf=4 Angular distributions of secondary neutrons 1325 1451 175 mt=2 1325 1451 176 Calculated with the statistical-model code casthy /1,8/. 1325 1451 177 mt=51-66 1325 1451 178 Incoherent sum of the statistical model and coupled-channel 1325 1451 179 model calculations/1/. Calculated with casthy and ecis or 1325 1451 180 jupitor-1. 1325 1451 181 mt=67-70 1325 1451 182 Assumed to be the same as mt=66. 1325 1451 183 1325 1451 184 mf=6 Energy-angle distributions of secondary particles 1325 1451 185 mt=16,22,28,91,203,207 1325 1451 186 Taken from JENDL fusion file. 1325 1451 187 1325 1451 188 mf=12 gamma-ray multiplicities (below 5.80993 MeV) 1325 1451 189 mt=51-70 1325 1451 190 Multiplicities were calculated from transition probabilities. 1325 1451 191 mt=102 1325 1451 192 Calculated from energy balance. 1325 1451 193 mt=103,107 1325 1451 194 Calculated by using the gnash code/1,12/. 1325 1451 195 1325 1451 196 mf=13 Gamma-ray production cross sections (above 5.80993 MeV) 1325 1451 197 mt=3 1325 1451 198 Calculated by the statistical model and coupled-channel model, 1325 1451 199 using the gnash code /12/ and the ecis /9/ or jupitor-1 code 1325 1451 200 /10/. Branching ratios for transitions between discrete levels1325 1451 201 were taken from ref./3/. Gamma-ray transition strength in the 1325 1451 202 continuum was calculated by the brink-axel giant resonance 1325 1451 203 model for E1 transition and by the Weisskopf single-particle 1325 1451 204 model for E2 and M1 transition/1/. 1325 1451 205 1325 1451 206 mf=14 Gamma-ray angular distributions 1325 1451 207 mt=3,51-70,102,103,107 1325 1451 208 Isotropic distribution was assumed. 1325 1451 209 1325 1451 210 mf=15 Gamma-ray spectra 1325 1451 211 mt=3,102,103,107 1325 1451 212 Calculated with the gnash code/1,12/ 1325 1451 213 1325 1451 214 References 1325 1451 215 1) Kitazawa H. et al.: Proc. Int. Conf. Nuclear Data for 1325 1451 216 Science and Technology, Mito, 1988, p.473, (1988). 1325 1451 217 2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992). 1325 1451 218 3) Yamamuro N.: JAERI-M 90-006 (1990). 1325 1451 219 4) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990). 1325 1451 220 5) ENSDF: Evaluated Nuclear Stracture Data File. 1325 1451 221 6) Nakagawa T.: JAERI-M 84-192 (1984). 1325 1451 222 7) Mughabghab S.F. et al.: "Neutron Cross Sections, Vol. 1 1325 1451 223 Part A", Academic Press (1981). 1325 1451 224 8) Igarasi S. and Fukahori T.: JAERI 1321 (1991). 1325 1451 225 9) Raynal J.: Computer Program ECIS79 for Coupled-Channel 1325 1451 226 Calculations, 1979 (unpublished). 1325 1451 227 10) Tamura T.: Rev. Mod. Phys., 37, 679 (1965). 1325 1451 228 11) Endt P.M. and Van der Leun C.: Nucl. Phys., A310, 1 (1978). 1325 1451 229 12) Young P.G. and Arthur E.D.: LA-6947 (1977). 1325 1451 230 13) Kitazawa H. et al.: unpublished. 1325 1451 231 14) Kitazawa H.: Computer Program Hikari for Direct-Semidirect 1325 1451 232 Capture Calculations, 1980 (unpublished). 1325 1451 233 15) Vonach H.: Nuclear Data Standards for Nuclear Measurements, 1325 1451 234 IAEA Technical Reports Series no. 227 (1983). 1325 1451 235 16) Shibata K.: Private communication (2000). 1325 1451 236 17) Yamamuro N.: Private communication (2000). 1325 1451 237 1 451 255 11325 1451 238 2 151 4 11325 1451 239 3 4 31 11325 1451 240 3 22 9 11325 1451 241 3 28 10 11325 1451 242 3 102 384 11325 1451 243 3 103 16 11325 1451 244 3 111 5 11325 1451 245 8 4 2 11325 1451 246 8 16 3 11325 1451 247 8 22 2 11325 1451 248 8 28 2 11325 1451 249 8 102 2 11325 1451 250 8 103 2 11325 1451 251 8 107 3 11325 1451 252 8 111 2 11325 1451 253 10 16 11 11325 1451 254 10 107 55 11325 1451 255 1325 1 099999 1325 0 0 0 1.302700+4 2.675000+1 0 0 1 01325 2151 1 1.302700+4 1.000000+0 0 0 1 01325 2151 2 1.000000-5 2.100000+5 0 0 0 01325 2151 3 2.500000+0 5.098000-1 0 0 0 01325 2151 4 1325 2 099999 1325 0 0 0 1.302700+4 2.675000+1 0 0 0 01325 3 4 1 0.000000+0-8.437990+5 0 0 1 831325 3 4 2 83 2 1325 3 4 3 8.753230+5 0.000000+0 8.771461+5 5.501020-4 8.807466+5 1.633115-31325 3 4 4 8.877645+5 3.731451-3 8.943946+5 5.698642-3 9.069598+5 9.387125-31325 3 4 5 9.180990+5 1.261455-2 9.379229+5 1.826253-2 9.530712+5 2.249853-21325 3 4 6 9.762537+5 2.885251-2 1.000000+6 3.520650-2 1.051880+6 3.982670-21325 3 4 7 1.052400+6 4.004270-2 1.072017+6 4.807328-2 1.090740+6 5.560196-21325 3 4 8 1.126731+6 6.971822-2 1.159196+6 8.206994-2 1.188370+6 9.287770-21325 3 4 9 1.214498+6 1.023345-1 1.261613+6 1.188839-1 1.298145+6 1.312959-11325 3 4 10 1.354935+6 1.499140-1 1.414210+6 1.685320-1 1.450790+6 1.798090-11325 3 4 11 1.510194+6 1.980865-1 1.564164+6 2.140793-1 1.663295+6 2.420667-11325 3 4 12 1.741745+6 2.630573-1 1.866411+6 2.945432-1 2.000000+6 3.260290-11325 3 4 13 2.292560+6 3.269960-1 2.370940+6 3.493775-1 2.493564+6 3.829498-11325 3 4 14 2.622530+6 4.165220-1 2.727244+6 4.477605-1 2.836140+6 4.789990-11325 3 4 15 3.000000+6 5.418330-1 3.092780+6 5.555710-1 3.116220+6 5.605960-11325 3 4 16 3.316927+6 6.109570-1 3.530560+6 6.613180-1 3.815400+6 7.281150-11325 3 4 17 4.000000+6 7.447590-1 4.103790+6 7.463980-1 4.205450+6 7.539340-11325 3 4 18 4.573710+6 7.755570-1 4.678800+6 7.833880-1 4.751100+6 7.943530-11325 3 4 19 4.991770+6 8.283880-1 5.000000+6 8.296120-1 5.347580+6 8.492870-11325 3 4 20 5.441980+6 8.539810-1 5.500000+6 8.576980-1 5.622380+6 8.653160-11325 3 4 21 5.635760+6 8.667640-1 5.641570+6 8.678460-1 5.705260+6 8.835730-11325 3 4 22 5.758060+6 9.006500-1 5.809830+6 9.170360-1 6.000000+6 9.514940-11325 3 4 23 6.500000+6 9.630320-1 7.000000+6 9.457160-1 7.500000+6 9.074350-11325 3 4 24 8.000000+6 8.716220-1 8.500000+6 8.485440-1 9.000000+6 8.267600-11325 3 4 25 1.000000+7 7.783030-1 1.048809+7 7.425235-1 1.100000+7 7.067440-11325 3 4 26 1.148913+7 6.714630-1 1.200000+7 6.361820-1 1.249000+7 5.871995-11325 3 4 27 1.300000+7 5.382170-1 1.349074+7 4.908720-1 1.400000+7 4.435270-11325 3 4 28 1.450000+7 4.066200-1 1.500000+7 3.709600-1 1.549193+7 3.454530-11325 3 4 29 1.600000+7 3.199460-1 1.700000+7 2.815280-1 1.800000+7 2.552680-11325 3 4 30 1.900000+7 2.352780-1 2.000000+7 2.163020-1 1325 3 4 31 1325 3 099999 1.302700+4 2.675000+1 0 0 0 01325 3 22 1 -1.009220+7-1.009220+7 0 0 1 171325 3 22 2 17 2 1325 3 22 3 1.046920+7 0.000000+0 1.050000+7 0.000000+0 1.100000+7 7.73590-131325 3 22 4 1.200000+7 1.730900-6 1.250000+7 1.658540-5 1.300000+7 8.935630-51325 3 22 5 1.350000+7 6.532790-4 1.400000+7 2.427690-3 1.420000+7 4.213560-31325 3 22 6 1.450000+7 8.487870-3 1.500000+7 1.935470-2 1.600000+7 4.779370-21325 3 22 7 1.680000+7 7.077490-2 1.700000+7 7.618800-2 1.800000+7 1.047670-11325 3 22 8 1.900000+7 1.317210-1 2.000000+7 1.535600-1 1325 3 22 9 1325 3 099999 1.302700+4 2.675000+1 0 0 0 01325 3 28 1 -8.271850+6-8.271850+6 0 0 1 211325 3 28 2 21 2 1325 3 28 3 8.580880+6 0.000000+0 8.600000+6 0.000000+0 9.000000+6 5.516470-71325 3 28 4 9.500000+6 1.425090-3 1.000000+7 9.935520-3 1.050000+7 2.658410-21325 3 28 5 1.100000+7 4.784900-2 1.200000+7 1.055600-1 1.250000+7 1.466020-11325 3 28 6 1.300000+7 1.930640-1 1.350000+7 2.392980-1 1.400000+7 2.796750-11325 3 28 7 1.420000+7 2.891280-1 1.450000+7 3.023840-1 1.500000+7 3.114040-11325 3 28 8 1.600000+7 3.176010-1 1.680000+7 3.217860-1 1.700000+7 3.211350-11325 3 28 9 1.800000+7 3.202560-1 1.900000+7 3.102890-1 2.000000+7 2.975910-11325 3 28 10 1325 3 099999 1.302700+4 2.675000+1 0 0 0 01325 3102 1 7.723690+6 7.723690+6 0 0 1 11431325 3102 2 1143 2 1325 3102 3 1.000000-5 1.160116+1 1.103037-5 1.104603+1 1.216691-5 1.051748+11325 3102 4 1.342055-5 1.001421+1 1.480336-5 9.535025+0 1.632865-5 9.078771+01325 3102 5 1.801111-5 8.644349+0 1.986691-5 8.230715+0 2.191394-5 7.836873+01325 3102 6 2.417189-5 7.461878+0 2.666248-5 7.104827+0 2.940971-5 6.764861+01325 3102 7 3.243999-5 6.441163+0 3.578251-5 6.132955+0 3.946943-5 5.839496+01325 3102 8 4.353624-5 5.560078+0 4.802208-5 5.294032+0 5.297013-5 5.040717+01325 3102 9 5.842801-5 4.799523+0 6.444825-5 4.569871+0 7.108881-5 4.351209+01325 3102 10 7.841358-5 4.143010+0 8.649308-5 3.944775+0 9.540506-5 3.756025+01325 3102 11 1.052353-4 3.576308+0 1.160784-4 3.405191+0 1.280388-4 3.242263+01325 3102 12 1.412315-4 3.087132+0 1.557836-4 2.939424+0 1.718351-4 2.798785+01325 3102 13 1.895404-4 2.664876+0 2.090701-4 2.537376+0 2.306120-4 2.415977+01325 3102 14 2.543736-4 2.300388+0 2.805835-4 2.190331+0 3.094939-4 2.085541+01325 3102 15 3.413832-4 1.985766+0 3.765583-4 1.890766+0 4.153577-4 1.800313+01325 3102 16 4.581549-4 1.714188+0 5.053618-4 1.632185+0 5.574328-4 1.554107+01325 3102 17 6.148689-4 1.479766+0 6.782232-4 1.408983+0 7.481052-4 1.341587+01325 3102 18 8.251877-4 1.277417+0 9.102125-4 1.216319+0 1.003998-3 1.158144+01325 3102 19 1.107447-3 1.102753+0 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