JENDL-5 (Neutron sublibrary (activation cs)) O - 16 0 0 0 0 8.016000+3 1.585750+1 0 0 6 1 825 1451 1 0.000000+0 0.000000+0 0 0 0 6 825 1451 2 1.000000+0 2.000000+7 0 0 10 5 825 1451 3 2.936000+2 0.000000+0 4 0 525 18 825 1451 4 8-O - 16 JAEA EVAL-DEC19 S.Kunieda 825 1451 5 DIST-DEC21 20200323 825 1451 6 ----JENDL-5 MATERIAL 825 825 1451 7 -----INCIDENT NEUTRON DATA 825 1451 8 ------ENDF-6 FORMAT 825 1451 9 825 1451 10 History 825 1451 11 19-12 Data are taken from R-matrix analysis with AMUR 825 1451 12 up to 6 MeV (S.Kunieda & O.Iwamoto) 825 1451 13 21-11 revised by O.Iwamoto 825 1451 14 (MF8/MT4,16,22,28,102-104,107) added 825 1451 15 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 825 1451 16 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 825 1451 17 825 1451 18 ****************************************************** 825 1451 19 * * 825 1451 20 * --- JENDL-5.0 --- * 825 1451 21 * * 825 1451 22 * Incident neutron data up to 200 MeV * 825 1451 23 * * 825 1451 24 ****************************************************** 825 1451 25 825 1451 26 Data are taken from R-matrix analysis with AMUR up to 6 MeV/1,2/. 825 1451 27 New data are the total, elastic scattering and (n,alpha) cross- 825 1451 28 sections with covariance. They are compiled in (MF,MT)= 825 1451 29 (3,1),(3,2),(3,107) : Cross sections 825 1451 30 (4,2) : Angular distribution 825 1451 31 (33,1),(33,2),(33,107) : Covariance data for cross sections 825 1451 32 825 1451 33 note: 825 1451 34 (n,alpha) cross-sections are larger than those in the previous 825 1451 35 library by ~35% due to the unitarity constraint from the 825 1451 36 R-matrix theory. 825 1451 37 825 1451 38 References 825 1451 39 1) S.Kunieda+, Nucl. Data Sheets 118:250 (2014). 825 1451 40 2) S.Kunieda+, Nucl. Data Sheets 123:159 (2015). 825 1451 41 825 1451 42 825 1451 43 ################################################## 825 1451 44 ### Descriptive texts of previous data ### 825 1451 45 ################################################## 825 1451 46 825 1451 47 825 1451 48 ****************************************************************** 825 1451 49 Descriptive data (E > 20 MeV) 825 1451 50 ****************************************************************** 825 1451 51 825 1451 52 ****************************************************** 825 1451 53 825 1451 54 --- JENDL-4.0/HE --- 825 1451 55 825 1451 56 High-energy Evaluation up to 200 MeV 825 1451 57 825 1451 58 ****************************************************** 825 1451 59 825 1451 60 History 825 1451 61 2015-03 Compiled by S.Kunieda 825 1451 62 825 1451 63 Above 20 MeV : taken from JENDL High-energy File 2007 /1/. 825 1451 64 Below 20 MeV : taken from JENDL-4.0 /2/. 825 1451 65 825 1451 66 References 825 1451 67 1) Watanabe,Y. et al.: J. Korean Phys. Soc., 59, 1443 (2011). 825 1451 68 2) Shibata,K. et al.: J. Nucl. Sci. Technol., 48, 1 (2011). 825 1451 69 825 1451 70 825 1451 71 ___________( Comments from JENDL High-energy File 2007 )__________ 825 1451 72 825 1451 73 ************************************************** 825 1451 74 * * 825 1451 75 * JENDL-HE HIGH ENERGY FILE * 825 1451 76 * * 825 1451 77 ************************************************** 825 1451 78 825 1451 79 NEUTRON EVALUATION UP TO 3 GEV 825 1451 80 USING mEXIFON, ALICE-F, AND JAM CODES 825 1451 81 T. Murata 825 1451 82 825 1451 83 HISTORY 825 1451 84 2003-05 New evaluation was made by T.Murata (AITEL). 825 1451 85 2003-10 Compilation was made by T.Fukahori (JAERI) and 825 1451 86 K.Kosako (SAEI) 825 1451 87 2005-05 The DDX of particle production was modified between 20- 825 1451 88 150 MeV by T.Murata (AITEL). 825 1451 89 2005-06 Compilation was made by K.Kosako (Shimizu Corp.) and 825 1451 90 T.Fukahori (JAERI). 825 1451 91 825 1451 92 MF=1 General Information 825 1451 93 MT=451 Description data and dictionary 825 1451 94 MF=3 Neutron Cross Sections 825 1451 95 MT=1 Total cross section 825 1451 96 Total cross section was calculated with ELIESE-3 code/1/ using 825 1451 97 potential given by Wilmore-Hodgeson/2/ in the incident neutron 825 1451 98 energy region below 65 MeV, and adjusted to connect smoothly 825 1451 99 to the cross section of JENDL-3.3 below 20MeV. between 65 MeV 825 1451 100 and 150 MeV, the cross section was calculeted with JLM model 825 1451 101 code developed by Chiba/3/. Above 150 MeV,the results of NMTC/ 825 1451 102 JAM code/4/ calculation were adopted. Calculated cross 825 1451 103 sections were modified a little to reproduce experimantal 825 1451 104 cross sections/5/. 825 1451 105 825 1451 106 MT=2 Elastic scattering cross section, 825 1451 107 MT=3 and MT=5 Non-elastic cross section 825 1451 108 Elastic scattering cross section and Non-elastic cross section 825 1451 109 were obtained in the calculations of total cross section men- 825 1451 110 tioned above. And modified a little to connect smoothly 825 1451 111 between each energy region. 825 1451 112 825 1451 113 MT=201: Neutron production cross section 825 1451 114 MT=202: Gamma-ray production cross section 825 1451 115 MT=203: Proton production cross section 825 1451 116 MT=204: Deuteron production cross section 825 1451 117 MT=205: Triton production cross section 825 1451 118 MT=206: He-3 production cross section 825 1451 119 MT=207: He-4 production cross section 825 1451 120 These cross sections were evaluated on the calculated results 825 1451 121 with a modified EXIFON(mEXIFON)/6/,DWUCK-4/7/ and NMTC/JAM 825 1451 122 codes and adjusted to reproduce experimental cross sections/8/ 825 1451 123 and also to connect smoothly to the cross section of JENDL-3.3 825 1451 124 at 20 MeV. For some reactions smoothly connection to JENDL-3.3 825 1451 125 values was abandoned because of contradiction with the experi- 825 1451 126 mental data in the present energy region. 825 1451 127 Gamma-ray production cross section was calculated with ALICE-F 825 1451 128 code/9/. 825 1451 129 825 1451 130 MF=4 Angular Distributions 825 1451 131 MT=2: Elastic Scattering 825 1451 132 Optical model and NMTC/JAM calculations described above,were 825 1451 133 made for angular distribution of elastic scattering. 825 1451 134 825 1451 135 MF=6 Product Energy-Angle Distributions 825 1451 136 MT= 5: Isotope Production Cross Section Ratios 825 1451 137 Production cross section of radio-nuclides, of which half 825 1451 138 lives are longer than 1 second; Be-7,Be-10,Be-11,C-10,C-11, 825 1451 139 C-14,N-13,N-16,O-14 and O-15 were evaluated on the calculated 825 1451 140 results with the above mentioned codes and normalized or 825 1451 141 adjusted to reproduce experimental data/10/. If no experimen- 825 1451 142 tal data were available, calculated results were adopted. The 825 1451 143 ratios of these cross sections to non-elastic cross section 825 1451 144 (MF=3,MT=5) are given in the file. 825 1451 145 For emission of neutron,photon,proton,deuteron,triton.He-3 and 825 1451 146 alpha particle, their energy-angle distributions are given in 825 1451 147 the laboratory system. 825 1451 148 Below 150 MeV, continuum energy spectrum of emitted particle 825 1451 149 in the cm system and ratios of precompoud process were calcu- 825 1451 150 lated with mEXIFON code and converted to the laboratory system 825 1451 151 with the systematics of Kalbach/11/. 825 1451 152 Angular distributions of the particles emitted by the follow- 825 1451 153 ing direct reaction were calculated with DWUCK-4 code, with 825 1451 154 parameters determined to reproduce experimental DDX/12/. 825 1451 155 825 1451 156 O16(n,d)N15(Ex=0.0MeV,1/2-) 825 1451 157 O16(n,d)N15(Ex=6.324MeV,3/2-) 825 1451 158 O16(n,t)N14(Ex=3.948MeV,1+) 825 1451 159 825 1451 160 These peaks were superimposed on continuum DDX. 825 1451 161 In the higher energy region, the DDX were calculated with 825 1451 162 NMTC/JAM code directly. Gamma-ray energy spectrum were 825 1451 163 calculated with ALICE-F code and angular distributions were 825 1451 164 assumed to be isotropic. 825 1451 165 825 1451 166 Additional isotope production cross sections below 20 MeV, which 825 1451 167 were evaluated presently and not included in JENDL-3.3 are given 825 1451 168 in the following. 825 1451 169 825 1451 170 O16+n, C14 production (eV,barn); 5 incident energy points 825 1451 171 825 1451 172 1.5539E+07 0.0000E+00 1.7000E+07 0.0000E+00 1.8000E+07 2.4420E-06 825 1451 173 1.9000E+07 3.1835E-05 2.0000E+07 1.8380E-04 825 1451 174 825 1451 175 O16+n, N16 production (eV,barn); 30 incident energy points 825 1451 176 825 1451 177 1.0244E+07 0.0000E+00 1.1000E+07 0.0000E+00 1.1250E+07 1.6900E-02 825 1451 178 1.1500E+07 3.4700E-02 1.1750E+07 7.9400E-02 1.1880E+07 7.9400E-02 825 1451 179 1.2000E+07 5.2700E-02 1.2250E+07 2.5100E-02 1.2500E+07 2.4100E-02 825 1451 180 1.2750E+07 2.6300E-02 1.3000E+07 3.1900E-02 1.3250E+07 4.0500E-02 825 1451 181 1.3500E+07 4.6000E-02 1.3750E+07 4.6000E-02 1.4000E+07 4.3700E-02 825 1451 182 1.4250E+07 4.0200E-02 1.4500E+07 3.6900E-02 1.4750E+07 3.5300E-02 825 1451 183 1.5000E+07 3.5300E-02 1.5250E+07 3.5000E-02 1.5500E+07 3.3000E-02 825 1451 184 1.5750E+07 3.1600E-02 1.6000E+07 3.0800E-02 1.6250E+07 3.0300E-02 825 1451 185 1.6500E+07 2.9000E-02 1.7000E+07 2.6400E-02 1.7500E+07 2.5600E-02 825 1451 186 1.8000E+07 2.4300E-02 1.9000E+07 2.2700E-02 2.0000E+07 2.2300E-02 825 1451 187 825 1451 188 O16+n, O15 production (eV,barn); 8 incident energy points 825 1451 189 825 1451 190 1.6652E+07 0.0000E+00 1.7000E+07 1.5500E-04 1.7500E+07 2.7200E-04 825 1451 191 1.8000E+07 4.5000E-04 1.8500E+07 7.1100E-04 1.9000E+07 1.0500E-03 825 1451 192 1.9500E+07 1.4900E-03 2.0000E+07 2.1000E-03 825 1451 193 825 1451 194 References 825 1451 195 /1/ Igarasi,S.: JAERI 1224 (1972) 825 1451 196 /2/ Wilmore,D,Hodgson,P.E.: Nucl.Physics.55,673(1964) 825 1451 197 /3/ Chiba,S.: Private communication 825 1451 198 /4/ Niita,K.: JAERI-Conf 2000-005(2000),p.98 825 1451 199 /5/ Auman,M.et al.: Phys.Rev.C5,1(1972) 825 1451 200 Measday,D.F.,Palmieri,J.N.: Nucl.Physics.85,129,(1966) 825 1451 201 /6/ Murata,T.: JAERI-Conf 97-005 (1997),p.286 825 1451 202 Kalka,H.: Z.Phys.A341,289(1992) 825 1451 203 /7/ Kunz,P.D.: Private communication. 825 1451 204 /8/ Proton; Benck,S.et al.: AD&ND Tables 72,1(1999), 825 1451 205 Deuteron; Benck,S.et al.: ibid., 825 1451 206 Triton; Benck,S.et al.: ibid., 825 1451 207 Shibata,S.et al.: INS-REP.1115(1995), 825 1451 208 He-3; Nakamura,T.et al.:Proc.ND for Sci.Tech.(Julich),p.714 825 1451 209 Alpha; Benck,S.et al.: ibid., 825 1451 210 Baba,M.et al.: Private communication 825 1451 211 /9/ Fukahori,T.: JAERI-M 92-039(1992),p.114 825 1451 212 /10/ C-14; Imamura,M. et al.: Nucl.Instr.Method B52,595(1990) 825 1451 213 N-16; DeJuren,J.A. et al.: Phys.Rev.127,1229(1962) 825 1451 214 O-15; Brill,O.D. et al.: DOC,136(1),55(1981) 825 1451 215 /11/ Kalbach,C.: Phys.Rev.C37(1988)2350 825 1451 216 /12/ Subramanian,T.S. et al.: Phys.Rev.C34,1580(1986), 825 1451 217 825 1451 218 825 1451 219 825 1451 220 ****************************************************************** 825 1451 221 Descriptive data (E < 20 MeV) 825 1451 222 ****************************************************************** 825 1451 223 825 1451 224 825 1451 225 HISTORY 825 1451 226 83-12 New evaluation for JENDL-3 825 1451 227 Sub-working group on evaluation of O-16, 825 1451 228 Working group on nuclear data for fusion, 825 1451 229 Japanese Nuclear Data Committee 825 1451 230 In charge 825 1451 231 sig-t Y.Nakajima K.Shibata(jaeri) 825 1451 232 sig-el T.Murata(naig) 825 1451 233 sig-in S.Tanaka(jaeri) 825 1451 234 capture T.Asami(jaeri) 825 1451 235 (n,2n),(n,p),(n,d),(n,alpha) Y.Kanda(kyu) 825 1451 236 Compilation 825 1451 237 Evaluated data were compiled by K.Shibata. 825 1451 238 84-07 Data of mf=4 (mt=16,91) were revised. 825 1451 239 Comment was also modified. 825 1451 240 87-01 Data of mf=3 (mt=51-64,67), mf=4 (mt=51-55) and mf=5(mt=16) 825 1451 241 were modified (S.Chiba, jaeri). Comment was also modified. 825 1451 242 90-10 mf=5 (except mt=91), mf=12, mt=102 modified. 825 1451 243 93-12 Capture and gamma production cross sections were modified. 825 1451 244 08-07 Total and elastics scattering cross sections were modified 825 1451 245 below 3 MeV. The elastic angular distributions were 825 1451 246 replaced with new R-matrix calculations between 100 keV and 825 1451 247 3 MeV. 825 1451 248 09-04 The (n,a) cross sections was modified. 825 1451 249 09-06 The interpolation of MF/MT=12/102 was changed to 2. 825 1451 250 ***** modified parts for JENDL-3.2 ****************************** 825 1451 251 (3,102) Reevaluated by K. Shibata. 825 1451 252 (3,2),(3,3) Recalculated 825 1451 253 (12,102) Modified due to energy conservation 825 1451 254 (12,51;57;62) 510 keV gammas incorporated 825 1451 255 (13,3) Reevaluated by T. Asami (de) 825 1451 256 ****************************************************************** 825 1451 257 ***** modified parts for JENDL Fusion File 96/1/26 ************* 825 1451 258 (3,102) Calculated by A. Mengoni (enea) 825 1451 259 (3,2),(3,3) Recalculated 825 1451 260 ****************************************************************** 825 1451 261 2002-1 Compiled by K.Shibata (jaeri) for JENDL-3.3. 825 1451 262 ***** modified parts for JENDL-3.3 2001/5/23 ******************* 825 1451 263 (1,451) Modified. 825 1451 264 (3,1),(3,2) Recalculated 825 1451 265 (3,16) Corrected 825 1451 266 The JENDL-3.2 data were ten times larger than the 825 1451 267 measurement /2/ by mistake. 825 1451 268 (3,3) Deleted 825 1451 269 (3,251) Deleted 825 1451 270 (4,2) Transformation matrices were deleted. 825 1451 271 (5,22),(5,28) Distributions at threshold were modified. 825 1451 272 Interpolation was changed to 22. 825 1451 273 (12,51-107) Calculated. 825 1451 274 (13,3) Deleted. 825 1451 275 (14,51-107) Prepared. 825 1451 276 (15,3) Deleted. 825 1451 277 (15,51-107) Calculated. 825 1451 278 (33,1-107) Taken from JENDL-3.2 covariance file except for 825 1451 279 mt=16. The covariance for mt=16 was revised on 825 1451 280 the basis of experimental data. 825 1451 281 (34,2) Taken from JENDL-3.2 covariance file. 825 1451 282 ****************************************************************** 825 1451 283 2009-04 Compiled by K.Shibata (jaea) for JENDL-4 825 1451 284 ***** modifications for JENDL-4 2008/07/02 ********************* 825 1451 285 (1,451) Modified 825 1451 286 (3,2) R-matrix calculations below 3 MeV 825 1451 287 (3,1) Re-calculated from partial cross sections 825 1451 288 (4,2) R-matrix calculations between 100 keV and 3 MeV 825 1451 289 (3,107) The data were replaced with those of ENDF/B-VII.0 825 1451 290 below 6.5 MeV. 825 1451 291 ****************************************************************** 825 1451 292 825 1451 293 mf=1 General information 825 1451 294 mt=451 Descriptive data 825 1451 295 825 1451 296 mf=2 Resonance parameters 825 1451 297 mt=151 Scattering radius only. 825 1451 298 825 1451 299 mf=3 Cross sections 825 1451 300 Thermal cross sections and resonance integrals at 300 K 825 1451 301 ---------------------------------------------------------- 825 1451 302 0.0253 eV res. integ. (*) 825 1451 303 (barns) (barns) 825 1451 304 ---------------------------------------------------------- 825 1451 305 Total 3.9624E+00 825 1451 306 Elastic 3.9646E+00 825 1451 307 n,gamma 1.8988E-04 6.7337E-04 825 1451 308 ---------------------------------------------------------- 825 1451 309 (*) Integrated from 0.5 eV to 10 MeV. 825 1451 310 825 1451 311 mt=1 Sig-t 825 1451 312 Below 3 MeV, the total cross section was calculated 825 1451 313 with the R-matrix theory. 825 1451 314 Above 3 MeV, based on the experimental data of 825 1451 315 Cierjacks et al./1/. 825 1451 316 ********************************************************* 825 1451 317 For JENDL-4, data were modified below 3 MeV. See above. 825 1451 318 ********************************************************* 825 1451 319 mt=2 Sig-el 825 1451 320 Below 3 MeV, calculated with the R-matrix theory. 825 1451 321 Above 3 MeV, the elastic scattering cross section was 825 1451 322 obtained by subtracting the reaction cross sections from 825 1451 323 the total cross section. 825 1451 324 ********************************************************* 825 1451 325 For JENDL-4, data were modified below 3 MeV. See above. 825 1451 326 ********************************************************* 825 1451 327 mt=4 Total inelastic 825 1451 328 Sum of mt=51 to 91. 825 1451 329 mt=16 (n,2n) 825 1451 330 Based on experimental data/2/. 825 1451 331 mt=51-79,91 Sig-in 825 1451 332 Shape of the excitation functions was calculated with 825 1451 333 the statistical model. 825 1451 334 The optical potential parameters are the following: 825 1451 335 V = 48.25-0.053E, Ws = 3.0 + 0.25E, Vso = 5.5 (MeV) 825 1451 336 r = 1.255 , rs = 1.352 , rso = 1.15 (fm) 825 1451 337 a = 0.536 , b = 0.205 , aso = 0.50 (fm). 825 1451 338 Level scheme 825 1451 339 no Energy(MeV) Spin-parity 825 1451 340 g.s. 0.0 0+ 825 1451 341 1 6.0490 0+ 825 1451 342 2 6.1300 3- 825 1451 343 3 6.9170 2+ 825 1451 344 4 7.1169 1- 825 1451 345 5 8.8720 2- 825 1451 346 6 9.6300 1- 825 1451 347 7 9.8470 2+ 825 1451 348 8 10.360 4+ 825 1451 349 9 10.960 0- 825 1451 350 10 11.080 3+ 825 1451 351 11 11.100 4+ 825 1451 352 12 11.520 2+ 825 1451 353 13 11.600 3- 825 1451 354 14 12.050 0+ 825 1451 355 15 12.440 1- 825 1451 356 16 12.530 2- 825 1451 357 17 12.800 0- 825 1451 358 18 12.970 2- 825 1451 359 19 13.020 2+ 825 1451 360 20 13.090 1- 825 1451 361 21 13.120 3- 825 1451 362 22 13.260 3- 825 1451 363 23 13.660 1+ 825 1451 364 24 13.870 4+ 825 1451 365 25 13.980 2- 825 1451 366 26 14.030 0+ 825 1451 367 27 14.100 3- 825 1451 368 28 14.300 4+ 825 1451 369 29 14.400 5+ 825 1451 370 Continuum levels were assumed above 14.4 MeV. 825 1451 371 Constant temperature of 3.4 MeV was used. 825 1451 372 For the inelastic scattering to the second and third 825 1451 373 levels, the (n,n')gamma data of Nordborg et al./3/ and 825 1451 374 Lundberg et al./4/ below 10 MeV. 825 1451 375 For mt=51 to 55, the 14 MeV cross sections were 825 1451 376 normalized to the experimental data/5/-/8/. 825 1451 377 Cross sections for mt=56-64 and 67 were normalized to 825 1451 378 reproduce the ddx data at 14 MeV/8/,/9/. 825 1451 379 mt=102 Capture 825 1451 380 1/v curve normalized to the recommended value in the 825 1451 381 4th edition of BNL-325 /10/ at 0.0253 eV. 825 1451 382 Between 1 eV and 1 MeV, model calculations (direct 825 1451 383 capture and resonance) were performed by A. Mengoni 825 1451 384 (enea)/28/. 825 1451 385 Above 1 MeV, a value of 0.1 mb was assumed by 825 1451 386 considering inverse reaction data. 825 1451 387 mt=103 (n,p) 825 1451 388 Based on experimental data/11/-/14/. 825 1451 389 mt=104 (n,d) 825 1451 390 Based on the evaluation of Foster, Jr. and Young /15/. 825 1451 391 mt=107 (n,alpha) 825 1451 392 Based on experimental data/3/,/16/-/21/. 825 1451 393 For JENDL-4, the measured (n,a) cross sections, which 825 1451 394 were coverted from the inverse-reaction data/18,21,32/, 825 1451 395 were compared with the existing libraries. As a result, 825 1451 396 it was found that the ENDF/B-VII.0 data reproduce the 825 1451 397 experimental data fairly well below 6.5 MeV. Therefore, 825 1451 398 we decided to replace the (n,a) data with those of 825 1451 399 ENDF/B-VII.0 below 6.5 MeV. Above 6.5 MeV, the cross 825 1451 400 sections remain unchanged from JENDL-3.3. 825 1451 401 825 1451 402 mf=4 Angular distributions of secondary neutrons 825 1451 403 mt=2 825 1451 404 10e-5 eV to 3 MeV R-matrix calculation 825 1451 405 3 MeV to 5 MeV Based on the experimental data of 825 1451 406 Lister and Sayres /22/. 825 1451 407 5 MeV to 9 MeV Multi-level formula/23/. 825 1451 408 9 MeV to 15 MeV Based on the experimental data of 825 1451 409 Glendinning et al./24/ 825 1451 410 15 MeV to 20 MeV Calculated with the spherical 825 1451 411 optical model. The potential 825 1451 412 parameters are the same as those 825 1451 413 given in Sig-in. 825 1451 414 ********************************************************* 825 1451 415 For JENDL-4, data were modified between 100 keV and 3 825 1451 416 MeV. See above. 825 1451 417 ********************************************************* 825 1451 418 mt=16 825 1451 419 Assumed to be isotropic in the laboratory system. 825 1451 420 mt=51-79 825 1451 421 Calculated with the statistical model. 825 1451 422 For mt=51, 52 and 55, experimental data/8/ at 14.2 MeV. 825 1451 423 For mt=53 and 54 ENDF/B-IV was adopted. 825 1451 424 mt=91 825 1451 425 Isotropic distributions in the center of mass system 825 1451 426 were transformed into the ones in the laboratory system. 825 1451 427 The formula is given in ref./25/. 825 1451 428 825 1451 429 mf=5 Energy distribution for secondary neutrons 825 1451 430 mt=16 825 1451 431 Evaporation spectrum was assumed. Constant temperature 825 1451 432 was deduced from the experimental data of Chiba et al. 825 1451 433 /26/ for Li-7 according to the Sqrt(E/a) law. 825 1451 434 mt=22,28 825 1451 435 Calcualted by GNASH /27/. 825 1451 436 mt=91 825 1451 437 Evaporation spectrum was assumed. Constant temperature 825 1451 438 of 3.4 MeV was determined from the stair case plotting. 825 1451 439 825 1451 440 mf=12 Photon production multiplicities 825 1451 441 mt=22,51-55,59,61,63,66-68,103,107 825 1451 442 Calculated with GNASH/27/. 825 1451 443 mt=102 825 1451 444 Calculated with CASTHY/29/. 825 1451 445 Below 280 keV, based on the data measured by Igashira 825 1451 446 et al./30/ 825 1451 447 825 1451 448 mf=14 Photon angular distributions 825 1451 449 mt=22,51-55,59,61,63,66-68,102,103,107 825 1451 450 Isotropic 825 1451 451 825 1451 452 mf=15 Photon energy distributions 825 1451 453 mt=22,103,107 825 1451 454 Calculated with GNASH/27/. 825 1451 455 mt=102 825 1451 456 Calculated with CASTHY/29/. 825 1451 457 825 1451 458 mf=33 Covariances of cross sections (ref. 31) 825 1451 459 mt=1 825 1451 460 Based on experimental data. A chi-value was 6.53. 825 1451 461 mt=2 825 1451 462 Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, 825 1451 463 and 107. 825 1451 464 mt=4 825 1451 465 Constructed from mt=51-91. 825 1451 466 mt=16 825 1451 467 Based on experimental data. 825 1451 468 mt=22 825 1451 469 Based on systematics. 825 1451 470 mt=28 825 1451 471 Based on systematics. 825 1451 472 mt=51-91 825 1451 473 The covariances were estimated by using kalman system. 825 1451 474 A chi-value was 2.45. 825 1451 475 For mt=52,53, based on experimental data between 7 and 825 1451 476 11 MeV. 825 1451 477 mt=102 825 1451 478 Based on experimental data. 825 1451 479 mt=103 825 1451 480 Based on experimental data. 825 1451 481 mt=104 825 1451 482 Based on experimental data. 825 1451 483 mt=107 825 1451 484 Based on experimental data. 825 1451 485 825 1451 486 mf=34 Covariances of angular distributions 825 1451 487 mt=2 825 1451 488 Based on experimental data and model calculations. 825 1451 489 825 1451 490 825 1451 491 References 825 1451 492 1) Cierjacks,S. et al.: Nucl. Instr. Meth., 169, 185 (1980). 825 1451 493 2) Brill,O.D. et al.: Soviet Phys. Doklady, 6, 24 (1961). 825 1451 494 3) Nordborg,C. et al.: Nucl. Sci. Eng., 66, 75 (1978). 825 1451 495 4) Lundberg,B. et al.: Phys. Scr. 2, 273 (1970). 825 1451 496 5) Bauer,R.W. et al.: Nucl. Phys., 47, 241 (1963). 825 1451 497 6) McDonald,W.J. et al.: Nucl. Phys., 75, 353 (1966). 825 1451 498 7) Meier,D. et al.: EXFOR 20907,007 (1969). 825 1451 499 8) Baba,M. et al.: "Nucl. Data for Basic and Applied Science", 825 1451 500 Santa Fe, 1985, p223. 825 1451 501 9) Takahashi,A. et al.: Oktavian report. 825 1451 502 10)Mughabghab,S.F. et al.: Neutron Cross Sections Vol.1, 825 1451 503 Academic Press, 1981. 825 1451 504 11)Bormann,N. et al.: First IAEA Conf. Nuclear Data for Reactors, 825 1451 505 1 (1967) 225. 825 1451 506 12)De Juren,J.A. et al.: Phys. Rev., 127, 1229 (1962). 825 1451 507 13)Seeman,K.W. et al.: Bull. Am. Phys. Soc., 6, 237 (1961). 825 1451 508 14)Martin,H.C. et al.: Phys. 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1.249520-1 6.870000+6 1.864210-1 6.920000+6 1.675490-1 825 3 4 7 6.940000+6 6.528530-2 7.000000+6 6.613760-2 7.040000+6 8.518760-2 825 3 4 8 7.090000+6 9.636110-2 7.150000+6 1.116970-1 7.200000+6 1.748770-1 825 3 4 9 7.250000+6 1.408960-1 7.300000+6 2.096890-1 7.350000+6 2.812010-1 825 3 4 10 7.353060+6 2.835730-1 7.353200+6 2.836780-1 7.400000+6 3.207070-1 825 3 4 11 7.450000+6 3.424580-1 7.480000+6 3.028630-1 7.500000+6 2.812460-1 825 3 4 12 7.550000+6 2.276560-1 7.565560+6 2.248770-1 7.565700+6 2.248510-1 825 3 4 13 7.600000+6 2.226500-1 7.650000+6 2.678130-1 7.700000+6 2.910320-1 825 3 4 14 7.750000+6 3.086920-1 7.800000+6 3.606710-1 7.820000+6 3.840290-1 825 3 4 15 7.850000+6 3.503640-1 7.910000+6 3.141830-1 7.960000+6 2.379810-1 825 3 4 16 8.000000+6 1.944520-1 8.030000+6 1.535670-1 8.050000+6 1.661600-1 825 3 4 17 8.150000+6 2.320820-1 8.200000+6 2.842690-1 8.240000+6 3.234550-1 825 3 4 18 8.250000+6 3.401050-1 8.260000+6 3.566320-1 8.340000+6 3.672770-1 825 3 4 19 8.350000+6 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