JENDL-5 (Neutron sublibrary (activation cs)) F - 19 0 0 0 0 9.019000+3 1.883500+1 0 0 6 1 925 1451 1 0.000000+0 0.000000+0 0 0 0 6 925 1451 2 1.000000+0 2.000000+7 0 0 10 5 925 1451 3 2.936000+2 0.000000+0 4 0 389 22 925 1451 4 9-F - 19 JAERI EVAL-JUL89 T.SUGI 925 1451 5 DIST-DEC21 20090828 925 1451 6 ----JENDL-5 MATERIAL 925 925 1451 7 -----INCIDENT NEUTRON DATA 925 1451 8 ------ENDF-6 FORMAT 925 1451 9 925 1451 10 History 925 1451 11 21-10 (MF,MT)=(4,2),(4,51),(4,52) are replaced by preliminary 925 1451 12 results of R-matrix analysis with AMUR up to 1.0 MeV 925 1451 13 (S.Kunieda) 925 1451 14 21-11 revised by O.Iwamoto 925 1451 15 (MF8/MT4,16,22,28,32,102-105,107) added 925 1451 16 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 925 1451 17 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 925 1451 18 925 1451 19 ****************************************************** 925 1451 20 * * 925 1451 21 * --- JENDL-5.0 --- * 925 1451 22 * * 925 1451 23 * Incident neutron data up to 200 MeV * 925 1451 24 * * 925 1451 25 ****************************************************** 925 1451 26 925 1451 27 Data evaulation was performed with an R-matrix code AMUR/1,2/ up 925 1451 28 to 1.0 MeV MeV. Experimental data fitted are as follows. 925 1451 29 (n,tot) : Larson+ (1976)/3/, CS 925 1451 30 (n,n1),(n,n2) : Lashuk+ (1994)/4/, CS 925 1451 31 (n,n1+n2) : Broder+ (1969)/5/, CS 925 1451 32 (n,n0+n1+n2) : Elwyn+ (1964)/6/, DA 925 1451 33 (n,g) : Gabbard+ (1959)/7/, CS 925 1451 34 (n,g) : Egorov+ (2005)/8/ at 0.0280 eV, CS 925 1451 35 However, the analysis was still preliminary as it was difficult 925 1451 36 to reproduce some of the cross-section measurements. Therefore, 925 1451 37 S.K. decided to adopt only the angular distribution of (n,n0), 925 1451 38 (n,n1),(n,n2) which shows better agreements with Elwyn+ than those 925 1451 39 in the previous files. 925 1451 40 925 1451 41 References 925 1451 42 1) S.Kunieda+, Nucl. Data Sheets 118:250 (2014). 925 1451 43 2) S.Kunieda+, Nucl. Data Sheets 123:159 (2015). 925 1451 44 3) Larson+, ORNL Tech. Report 5612 (1976). 925 1451 45 4) Lashuk+, taken from EXFOR (1994). 925 1451 46 5) Broder+, Technical Report, Obninsk 155 (1969). 925 1451 47 6) Elwyn+, Nucl. Phys. 59:113 (1964). 925 1451 48 7) Gabbard+, Phys Rev. 114:201 (1959). 925 1451 49 8) Egorov+, NIM A 545:296 (2005). 925 1451 50 925 1451 51 925 1451 52 ################################################## 925 1451 53 ### Descriptive texts of previous data ### 925 1451 54 ################################################## 925 1451 55 925 1451 56 925 1451 57 ****************************************************************** 925 1451 58 Descriptive data (E > 20 MeV) 925 1451 59 ****************************************************************** 925 1451 60 925 1451 61 ****************************************************** 925 1451 62 925 1451 63 --- JENDL-4.0/HE --- 925 1451 64 925 1451 65 High-energy Evaluation up to 200 MeV 925 1451 66 925 1451 67 ****************************************************** 925 1451 68 925 1451 69 History 925 1451 70 2015-03 Compiled by S.Kunieda 925 1451 71 925 1451 72 Above 20 MeV : taken from JENDL High-energy File 2007 /1/. 925 1451 73 Below 20 MeV : taken from JENDL-4.0 /2/. 925 1451 74 925 1451 75 References 925 1451 76 1) Watanabe,Y. et al.: J. Korean Phys. Soc., 59, 1443 (2011). 925 1451 77 2) Shibata,K. et al.: J. Nucl. Sci. Technol., 48, 1 (2011). 925 1451 78 925 1451 79 925 1451 80 ___________( Comments from JENDL High-energy File 2007 )__________ 925 1451 81 925 1451 82 ************************************************** 925 1451 83 * * 925 1451 84 * JENDL-HE HIGH ENERGY FILE * 925 1451 85 * * 925 1451 86 ************************************************** 925 1451 87 925 1451 88 925 1451 89 NEUTRON EVALUATION UP TO 3 GEV 925 1451 90 USING GNASH-ECN AND JAM CODES 925 1451 91 K. Kosako 925 1451 92 __________________________________________________________________ 925 1451 93 925 1451 94 In the evaluation of high-energy region, different theoretical 925 1451 95 model codes were used in accordance with incident energies: (I) 925 1451 96 intermediate energies up to 250 MeV, and (II) high energies above 925 1451 97 150 MeV. 925 1451 98 A major code used in (I) was the GNASH code [1] based on 925 1451 99 statistical Hauser-Feshbach plus preequilibrium models. Optical 925 1451 100 model calculations were performed using the ECIS96 code [2], 925 1451 101 in which a spherical optical potential was used and the parameters 925 1451 102 were adjusted so as to reproduce experimental data. This code was 925 1451 103 also employed for DWBA calculation of direct inelastic scattering 925 1451 104 cross sections. Experimental data for both neutrons and protons 925 1451 105 were reproduced well by these calculations. Thus, the calculated 925 1451 106 results were adopted as the evaluated values of total cross 925 1451 107 sections, elastic and inelastic scattering cross sections, and 925 1451 108 total reaction cross sections up to 250 MeV. Transmission 925 1451 109 coefficients obtained by the optical model calculation were used 925 1451 110 in GNASH calculations of particle and gamma ray emission cross 925 1451 111 sections and isotope production cross sections up to 250 MeV. 925 1451 112 Elastic cross sections and angular distributions refered the 925 1451 113 result by the TOTELA code [3] based on systematics. 925 1451 114 In (II), the high energy nuclear reaction code JAM [4] plus 925 1451 115 statistical decay model (GEM) [5] was employed. Also, the TOTELA 925 1451 116 code was employed as a tool for evaluation of total, elastic, and 925 1451 117 proton reaction cross-sections. 925 1451 118 Gamma-ray energy spectra were calculated with ALICE-F code [6] 925 1451 119 and angular distributions were assumed to be isotropic. 925 1451 120 925 1451 121 References 925 1451 122 925 1451 123 [1] P.G. Young et al., LA-12343-MS, LANL (1992). 925 1451 124 [2] J. Raynal, IAEA SMR-9/8, p281 (1970). 925 1451 125 [3] T. Fukahori and K. Niita, INDC(NDS)-416. 925 1451 126 [4] Y. Nara, et al., Phys. Rev. C61, 024901 (1999). 925 1451 127 [5] S. Furihata, Nucl. Instr. and Meth. B171, p251 (2000). 925 1451 128 [6] T. Fukahori, JAERI-M 92-039, p114 (1992). 925 1451 129 __________________________________________________________________ 925 1451 130 925 1451 131 925 1451 132 925 1451 133 ****************************************************************** 925 1451 134 Descriptive data (E < 20 MeV) 925 1451 135 ****************************************************************** 925 1451 136 925 1451 137 ---------------------------------------- 925 1451 138 (MF,MT)=(4,2),(4,51),(4,52) were repalced by results of preliminar 925 1451 139 R-matrix analysis with AMUR up to 1 MeV 925 1451 140 2021.10.06 S.Kunieda 925 1451 141 ---------------------------------------- 925 1451 142 925 1451 143 =========================================================== 925 1451 144 The data were taken from JENDL-3.3. 925 1451 145 =========================================================== 925 1451 146 925 1451 147 925 1451 148 HISTORY 925 1451 149 83-11 Evaluation for JENDL-2 was performed by Sugi and Nishimura 925 1451 150 (jaeri)/1/. 925 1451 151 89-07 Resonance parameters and total cross section were 925 1451 152 re-evaluated for JENDL-3. 925 1451 153 89-07 Compiled by T. Narita (jaeri). 925 1451 154 94-06 JENDL-3.2. 925 1451 155 Gamma prodction data modified by T.Asami (Data Eng.). 925 1451 156 Other data were mainly adopted from JENDL fusion file. 925 1451 157 Compiled by T.Nakagawa (ndc/jaeri) 925 1451 158 925 1451 159 ***** Modified parts for JENDL-3.2 ******************** 925 1451 160 (3,2), (3,4), (3,22), (3,28), (3,52-91), (3,104), (3,251) 925 1451 161 All angular distributions 925 1451 162 All energy distributions 925 1451 163 New evaluation fot gamma-ray production data 925 1451 164 *********************************************************** 925 1451 165 ------------------------------------------------------------- 925 1451 166 JENDL fusion file /2/ (as of Jun. 1994) 925 1451 167 Evaluated and compiled by S.Chiba (ndc/jaeri). 925 1451 168 925 1451 169 The calculations have been carried out with the sincros-II 925 1451 170 code system (dwucky, egnash and casthy2y) /3/. the 925 1451 171 following set of omps were selected: 925 1451 172 n : Yamamuro (modified Walter-Guss) /3/ 925 1451 173 p : Perey and Walter-Guss combined /4/ 925 1451 174 d : Lohr-Haeberli /5/ 925 1451 175 t : Becchetti-Greenlees /6/ 925 1451 176 he-3 : Becchetti-Greenlees /6/ 925 1451 177 alpha : Lemos set modified by Arthur-Young /7/ 925 1451 178 925 1451 179 The following values of level density parameters (1/MeV) 925 1451 180 were used to reproduce the ddx at 14 MeV: 925 1451 181 925 1451 182 F-20 F-19 F-18 O-19 O-18 O-17 N-17 N-16 N-15 N-14 C-15 C-14 925 1451 183 4.49 3.50 2.50 2.50 3.00 2.99 3.51 2.00 2.00 2.03 2.84 2.46 925 1451 184 925 1451 185 The data were taken from JENDL-3.1 except for the following: 925 1451 186 925 1451 187 mf=3, mt= 2: adjusted to conserve the total c.s. 925 1451 188 mf=3, mt= 3: calculated as a sum of reaction c.s. 925 1451 189 mf=3, mt= 4: calcaulated as a sum of inelastic c.s. 925 1451 190 mf=3, mt=22, 28, 32, 91 : taken from the sincros-II 925 1451 191 calculation 925 1451 192 mf=3, mt=52: replaced by the sincros-II calculation above 925 1451 193 2.5 mev 925 1451 194 mf=3, mt=53-60: replaced by the sincros-II calculation 925 1451 195 mf=3, mt=203,204,205,207: taken from the sincros-II calc. 925 1451 196 mf=4, mt= 2: repalced by the sincros-II calculation 925 1451 197 mf=6, mt=22, 28, 32, 91 : taken from the sincros-II 925 1451 198 calculation. Kumabe's systematics was used. 925 1451 199 mf=6, mt=203,204,205,207: taken from the sincros-II 925 1451 200 calculation. Kalbach's systematics was used. 925 1451 201 ------------------------------------------------------------- 925 1451 202 00-10 JENDL-3.3 925 1451 203 Compiled by K.Shibata (jaeri). 925 1451 204 ***** Modified parts for JENDL-3.3 ************************ 925 1451 205 (1,451) Updated. 925 1451 206 (3,203-207) Calculated. 925 1451 207 (3,251) Deleted. 925 1451 208 (4,2) Transformation matrix deleted. 925 1451 209 (4,16-28) Deleted. 925 1451 210 (5,16-28) Deleted. 925 1451 211 (6,16-28) Taken from JENDL fusion file. 925 1451 212 (6,203-207) Taken from JENDL fusion file. 925 1451 213 ************************************************************ 925 1451 214 925 1451 215 925 1451 216 mf=1 General information 925 1451 217 mt=451 Descriptive data and dictionary 925 1451 218 925 1451 219 mf=2 Resonance parameters 925 1451 220 mt=151 Resolved resonance parameters : 1.0e-5 eV - 100 keV 925 1451 221 The multi-level Breit-Wigner formula was used. 925 1451 222 Res. energies and gam-n : The first two levels were based on 925 1451 223 Johnson et al. /8/. The 3rd and 4th levels were adjusted 925 1451 224 so as to fit to the experimental data of Larson et al./9/ 925 1451 225 Gam-g : The first three levels were based on Macklin and 925 1451 226 Winters /10/. The 4th level was adjusted so as to fit to 925 1451 227 the recommended thermal capture cross section of 925 1451 228 Mughabghab et al./11/. 925 1451 229 Scattering radius: 5.525 fm 925 1451 230 925 1451 231 calculated 2200-m/s cross sections and res. integrals. 925 1451 232 2200 m/s res. integ. 925 1451 233 elastic 3.643 b - 925 1451 234 capture 9.6 milli-b 19.5 milli-b 925 1451 235 total 3.652 b - 925 1451 236 925 1451 237 mf=3 Neutron cross sections 925 1451 238 mt=1 Total cross section 925 1451 239 Below 100 keV: no background. 925 1451 240 Above 100 keV: based on the experimental data of Larson et 925 1451 241 al./9/ 925 1451 242 mt=2 Elastic scattering cross section 925 1451 243 Derived by subtracting the nonelastic cross section from 925 1451 244 the total cross section. 925 1451 245 mt=4 Total inelastic scattering cross section 925 1451 246 Sum of mt=51-60,91. 925 1451 247 mt=16 (n,2n) cross section 925 1451 248 Calculated by fitting the Pearlstein's function /12/ to the 925 1451 249 experimental data. 925 1451 250 mt=22 (n,n' alpha) and (n,alpha n') cross sections 925 1451 251 Calculated by the sincros-II code system. 925 1451 252 mt=28 (n,n' p) and (n,p n') cross sections 925 1451 253 Calculated by the sincros-II code system. 925 1451 254 mt=32 (n,n'd) cross secton 925 1451 255 Calculated by the sincros-II code system. 925 1451 256 mt=51-60 Inelastic scattering cross sections 925 1451 257 mt=51 (taken from JENDL-3.1) 925 1451 258 Up to 1 MeV : based on the experimental data of Broder 925 1451 259 et al. /13/. 925 1451 260 1 MeV - 5.5 MeV : calculated with the Hauser-Feshbach 925 1451 261 method (eliese-3 /14/) taking into account 925 1451 262 (n,alpha) and (n,p) as competing processes. The 925 1451 263 level scheme of F-19, N-16 and O-19 was taken from 925 1451 264 Ajzenberg-Selove /15,16/. The optical potential 925 1451 265 parameters are : 925 1451 266 V = 51.56 - 1.492*E (MeV), 925 1451 267 Ws = 11.82 (MeV), 925 1451 268 Vso= 10.0 (MeV), 925 1451 269 r0 = rs = rso = 1.31 (fm), 925 1451 270 a = aso = 0.66 (fm), 925 1451 271 b = 0.47 (fm). 925 1451 272 The level density parameter of 3.609 (1/MeV)/17/ and 925 1451 273 pairing energy of 2.52 MeV /18/ were used. 925 1451 274 mt=52 925 1451 275 Up to 2.5 MeV: taken from JENDL-3.1, which is based on the 925 1451 276 data of Broder et al. /13/. 925 1451 277 Above 2.5 MeV: calculated by the sincros-II code system. 925 1451 278 mt=53 - 60 925 1451 279 Calculated by the sincros-II code system. 925 1451 280 The sincros-II calculation adopted the following discrete 925 1451 281 levels. The levels with L and Beta-L include the 925 1451 282 contribution of direct inelastic scattering, which was 925 1451 283 calculated assuming the weak-coupling model by the DWBA 925 1451 284 method: 925 1451 285 925 1451 286 ---------------------------------------------- 925 1451 287 mt ex(MeV) spin-parity L beta-L 925 1451 288 ---------------------------------------------- 925 1451 289 2 0.0 1/2+ 925 1451 290 51 0.1099 1/2- 925 1451 291 52 0.1972 5/2+ 2 0.4 925 1451 292 53 1.3457 5/2- 925 1451 293 54 1.4585 3/2- 925 1451 294 55 1.5541 3/2+ 2 0.6 925 1451 295 56 2.7798 9/2+ 4 0.4 925 1451 296 57 3.9071 3/2+ 925 1451 297 58 3.9985 7/2- 925 1451 298 59 4.0325 9/2- 925 1451 299 60 4.3777 7/2+ 4 0.4 925 1451 300 ---------------------------------------------- 925 1451 301 925 1451 302 mt=91 Inelastic to continuum 925 1451 303 Calculated with sincros-II code system. 925 1451 304 mt=102 Capture cross section 925 1451 305 Below 100 keV : no background. 925 1451 306 100 keV - 1.87 MeV : based on the experimental data of 925 1451 307 Gabbard et al. /19/. 925 1451 308 1.87 MeV - 20 MeV : assumed to decrease with 1/v law. 925 1451 309 mt=103 (n,p) cross section 925 1451 310 Up to 9 MeV : based on the experimental data of Bass et 925 1451 311 al. /20/. 925 1451 312 9 MeV - 20 MeV : calculated with the statistical model by 925 1451 313 using Pearlstein' empirical formula. 925 1451 314 mt=104 (n,d) cross section 925 1451 315 Calculated by the sincros-II code system. 925 1451 316 mt=105 (n,t) cross section 925 1451 317 Calculated by the sincros-II code system. 925 1451 318 mt=107 (n,alpha) cross section 925 1451 319 Below 9 MeV, based on the following experimental data: 925 1451 320 Up to 4MeV Davis et al. /21/, 925 1451 321 4MeV - 5.5MeV Smith et al. /22/, 925 1451 322 5.5MeV - 9MeV Bass et al. /20/. 925 1451 323 Above 9 MeV, calculated with the Pearlstein's formula. 925 1451 324 mt=203 Total proton production 925 1451 325 Sum of mt=28 and 103. 925 1451 326 mt=204 Total deuteron production 925 1451 327 Sum of mt=32 and 104. 925 1451 328 mt=205 Total triton production 925 1451 329 Equal to mt=105. 925 1451 330 mt=207 Total alpha production 925 1451 331 Sum of mt=22 and 107. 925 1451 332 925 1451 333 mf=4 Angular distributions of secondary neutrons 925 1451 334 mt=2 925 1451 335 Calculated with optical model by the sincros-II code system. 925 1451 336 mt=51-60 925 1451 337 Calculated by the sincros-II code system. 925 1451 338 925 1451 339 mf=6 Energy-angle distributions of secondary particles 925 1451 340 mt=16,22,28,32,91 925 1451 341 Calculated usingt the sincros-II code system and Kumabe's 925 1451 342 systematics /23/. 925 1451 343 mt=203,204,205,207 925 1451 344 Based on Kalbach's systematics/24/. 925 1451 345 925 1451 346 mf=12 Photon production multiplicities 925 1451 347 mt=51-60, 102, 103, 107 925 1451 348 Calculated with the gnash code /7/. 925 1451 349 925 1451 350 mf=13 Photon production cross sections 925 1451 351 mt=3 925 1451 352 Calculated with the gnash code/7/. 925 1451 353 925 1451 354 mf=14 Photon angular distributions 925 1451 355 mt=3,51-60,102,103,107 925 1451 356 Isotropic 925 1451 357 925 1451 358 mf=15 Photon energy distributions 925 1451 359 mt=3,102,103.107 925 1451 360 Calculated with the gnash code/7/. 925 1451 361 925 1451 362 References 925 1451 363 1) Sugi T. and Nishimura K.: JAERI-M 7253 (1977), English trans- 925 1451 364 lation : ORNL-TR-4605. 925 1451 365 2) Chiba, S. et al.: JAERI-M 92-027, p.35(1992). 925 1451 366 3) Yamamuro, N.: JAERI-M 90-006 (1990). 925 1451 367 4) Walter, R.L. and Guss, P.P.: Int. Conf. on Nucl. Data for 925 1451 368 Basic and Applied Science, Santa Fe, p.1079 (1986). 925 1451 369 5) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974). 925 1451 370 6) Becchetti, F.D. and Greenlees, G.W.: "Polarization Phenomena 925 1451 371 in Nuclear Reactions", Univ. of Wisconsin Press, p.682 925 1451 372 (1971). 925 1451 373 7) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980). 925 1451 374 8) Johnson C.H. et al.: ORNL-5025 (1975). 925 1451 375 9) Larson D.C. et al.: ORNL/TM-5612 (1976). 925 1451 376 10) Macklin R.L. and Winters R.R.: Phys. Rev. C7, 1766 (1973). 925 1451 377 11) Mughabghab S.F. et al.: Neutron Cross Sections, Vol.1, Part A, 925 1451 378 Z=1-60, Academic Press (1981). 925 1451 379 12) Pearlstein S.: Nucl. Sci. Eng. 23, 238 (1965). 925 1451 380 13) Broder et al.: 70 Helsinki Conf. 2, 295 (1970). 925 1451 381 14) Igarasi S.: JAERI 1224 (1972). 925 1451 382 15) Ajzenberg-Selove F.: Nucl. Phys. A166, 1 (1971). 925 1451 383 16) Ajzenberg-Selove F.: Nucl. Phys. A190, 1 (1972). 925 1451 384 17) Abdelmalek N.N. and Stavinsky V.S.: Nucl. Phys. 58, 601 (1964) 925 1451 385 18) Newton T.D.: Can. J. Phys. 34, 804 (1956). 925 1451 386 19) Gabbard F. et al.: Phys. Rev. 114, 201 (1959). 925 1451 387 20) Bass R. et al.: EANDC(E) 66-64. 925 1451 388 21) Davis E.A. et al.: Nucl. Phys. 27, 448 (1961). 925 1451 389 22) Smith D.L. et al.: Phys. Rev. 117, 514 (1960). 925 1451 390 23) Kumabe, I. et al.: Nucl. Sci. and Eng., 104, 280 (1990). 925 1451 391 24) Kalbach C. : Phys. Rev. C37, 2350(1988). 925 1451 392 925 1451 393 1 451 415 1 925 1451 394 2 151 4 1 925 1451 395 3 4 34 1 925 1451 396 3 16 10 1 925 1451 397 3 22 9 1 925 1451 398 3 28 7 1 925 1451 399 3 32 5 1 925 1451 400 3 102 395 1 925 1451 401 3 103 21 1 925 1451 402 3 104 8 1 925 1451 403 3 105 8 1 925 1451 404 3 107 20 1 925 1451 405 8 4 2 1 925 1451 406 8 16 2 1 925 1451 407 8 22 2 1 925 1451 408 8 28 2 1 925 1451 409 8 32 2 1 925 1451 410 8 102 2 1 925 1451 411 8 103 2 1 925 1451 412 8 104 2 1 925 1451 413 8 105 2 1 925 1451 414 8 107 2 1 925 1451 415 925 1 099999 925 0 0 0 9.019000+3 1.883500+1 0 0 1 0 925 2151 1 9.019000+3 1.000000+0 0 0 1 0 925 2151 2 1.000000-5 1.000000+5 0 0 0 0 925 2151 3 5.000000-1 5.525000-1 0 0 0 0 925 2151 4 925 2 099999 925 0 0 0 9.019000+3 1.883500+1 0 0 0 0 925 3 4 1 0.000000+0-1.100000+5 0 0 1 91 925 3 4 2 91 2 925 3 4 3 1.158400+5 0.000000+0 1.250000+5 2.000000-1 1.500000+5 6.000000-1 925 3 4 4 2.000000+5 1.200000+0 2.076700+5 1.506800+0 2.400000+5 3.100000+0 925 3 4 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