B-1604,ISTC, JINER Np-237 9346 0 0 0 9.323700+4 2.350120+2 1 1 0 49346 1451 1 0.000000+0 1.000000+0 0 0 0 69346 1451 2 1.000000+0 2.000000+7 3 0 10 39346 1451 3 0.000000+0 0.000000+0 0 0 516 899346 1451 4 93-Np-237 JINER EVAL-SEP09 V.M.Maslov et al. 09346 1451 5 DIST-SEP09 20090930 9346 1451 6 ----ENDF/B-III MATERIAL 9346 9346 1451 7 -----INCIDENT NEUTRON DATA 9346 1451 8 ------ENDF-6 FORMAT 9346 1451 9 Evaluation is accomplished under the Project Agreement 9346 1451 10 B-1604 with the International Science and Technology by9346 1451 11 V.M. Maslov, V.G.Pronyaev, N.A. Tetereva, A.M. Kolesov,9346 1451 12 of JINER(Belarus)in collaboration with 9346 1451 13 T. Granier, CEA/DAM (France), F.-J. Hambsch, JRC IRMM 9346 1451 14 (Belgium), A.L. Nichols, IAEA (Austria) 9346 1451 15 9346 1451 16 HISTORY 9346 1451 17 Our previous activity regarding 237-Np neutron data 9346 1451 18 concentrated on the yield of 236(s)Np short-lived isomer, 9346 1451 19 branching ratio and fission data analysis in MeV-energy 9346 1451 20 range /1,2/ 9346 1451 21 9346 1451 22 2009-09 Evaluated are unresolved resonance parameters, 9346 1451 23 smooth cross sections, neutron angular distributions, 9346 1451 24 secondary neutron spectra, prompt fission neutron spectra,9346 1451 25 prompt fission neutron multiplicity, delayed fission 9346 1451 26 neutron multiplicity. 9346 1451 27 Resolved neutron parameters of JENDL-3.3 are adopted 9346 1451 28 MF=1 General information 9346 1451 29 MT=451 Descriptive data and dictionary 9346 1451 30 MT=452 fission neutron multiplicity 9346 1451 31 sum of MT=455 and MT=456 9346 1451 32 MT=455 delayed fission neutron multiplicity is obtained asa 9346 1451 33 polinomial fit of measured data by Piksaikin et al. /3/ 9346 1451 34 and Bobkov et al. /4/. 9346 1451 35 **** 9346 1451 36 *** 9346 1451 37 *** 9346 1451 38 MT=456 prompt fission neutron multiplicity 9346 1451 39 GMA code /5/ was used to fit measured data by Veeser /6/,9346 1451 40 Frehaut et al. /7/, Mueler /8/, Malinovskii et al. /9/, 9346 1451 41 Khokhlov et al. /10/, Boikov et al. /11/, Thierens /12/. 9346 1451 42 At incident neutron energies higher than (n,nf) reaction 9346 1451 43 threshold slight bump in nu-bar was reproduced taking 9346 1451 44 into account partial contributions of (n,F) and (n,nf) 9346 1451 45 reactions /13/. 9346 1451 46 9346 1451 47 MF=2 Resonance Parameters 9346 1451 48 MT=151 Resolved and unresolved resonance parameters are adopted 9346 1451 49 from JENDL-3.3 and modified as follows: 9346 1451 50 1) Resolved resonance parameters for MLBW formula (below 500 eV)9346 1451 51 Neutron and capture widths: Gressier et al. /14/ and 9346 1451 52 Auchampaugh et al. /15/ 9346 1451 53 Fission width: Borzakov et al./16/, Dermendjiev et al. 9346 1451 54 /17/ and Auchampaugh et al. /15/ 9346 1451 55 Parameters of the -0.56- and 0.49-eV resonances were 9346 1451 56 adjusted to reproduce thermal fission and capture cross 9346 1451 57 sections by Kozharin et al. /18/ and Wagemans et al. /19,20/9346 1451 58 Scattering radius of 9.516 fm was adopted, thermal total 9346 1451 59 cross section, calculated with Gressier et al./14/ 9346 1451 60 parameters equals XXXXXX barn 9346 1451 61 9346 1451 62 2200-M/S cross sections and calculated resonance integrals: 9346 1451 63 2200 m/s(b) Res. integ.(b) 9346 1451 64 TOTAL 175.79 9346 1451 65 ELASTIC 14.057 - 9346 1451 66 FISSION 0.0204 6.94 9346 1451 67 CAPTURE 61.71 654.26 9346 1451 68 9346 1451 69 9346 1451 70 2) Unresolved resonance parameters (500 eV - 76.243 keV) 9346 1451 71 The average resonance parameters were determined in /21/ 9346 1451 72 to reproduce average cross sections 9346 1451 73 (Gg=0.0375 eV, D_obs=0.563 eV.): 9346 1451 74 9346 1451 75 total: Auchampaugh et al. /15/ 9346 1451 76 and optical model calculations, with coupled 9346 1451 77 channels potential parameters, fitting data by 9346 1451 78 Kornilov et al. /22/ in the energy range 0.5-9 9346 1451 79 MeV. 9346 1451 80 fission: Tovesson and Hill /23/, Yamanaka et al. /24/, 9346 1451 81 Plattard /25/, Carlson/26/, 9346 1451 82 Brown /27/, Hoffman /28/ 9346 1451 83 capture: Weston and Todd /29/ and Eshch et al. /30/, 9346 1451 84 Kobayashi et al. /31/ 9346 1451 85 9346 1451 86 9346 1451 87 MF=3 Neutron crosss ections 9346 1451 88 From .5 up to 76 keV evaluated cross sections were repre-9346 1451 89 sented with energy-dependent unresolved resonance parame-9346 1451 90 ters (EDURP). EDURP reproduce total, scattering, fission,9346 1451 91 capture and inelastic scattering cross sections, calcu- 9346 1451 92 lated with statistical model. The latter is used in 9346 1451 93 higher energy domain. 9346 1451 94 9346 1451 95 MT= 1, 2, 4, 51-76, 91 - total, elastic and inelastic 9346 1451 96 scattering cross sections. 9346 1451 97 Total, elastic and direct inelastic for rotational ground9346 1451 98 state band levels MT=51,53,55(coupled levels), as well 9346 1451 99 as optical transmission coefficients are obtained 9346 1451 100 with a rigid rotator model coupled channel calculations. 9346 1451 101 Direct inelastic contributions were added incoherently 9346 1451 102 to Hauser-Feshbach calculated values of compound nucleus 9346 1451 103 inelastic scattering cross sections. 9346 1451 104 Total inelastic and continuum inelastic cross sections 9346 1451 105 reproduce inelastic scattering data by Kornilov et al/22/9346 1451 106 for the excitation of specific groups of continuum levels9346 1451 107 The sharp increase evidenced in the inelastic data /22/ 9346 1451 108 is explained by the excitation of three quasi-particle 9346 1451 109 states in residual nuclide Np-237 /32/. 9346 1451 110 The deformed optical potential adopted was that for 9346 1451 111 238-U, /33/, then the parameters were slightly varied 9346 1451 112 to describe measured total data /15,22,34/. Partitioning 9346 1451 113 of the total cross section into reaction and scattering 9346 1451 114 cross sections allows consistent description of fission 9346 1451 115 an inelastic cross sections in 1-3 MeV energy range 9346 1451 116 within a statistical model. 9346 1451 117 Strength function So = 1.0105x10-4(EV)-1/2 at 0.1 keV. 9346 1451 118 9346 1451 119 VR=(45.722-0.334xE) MeV; RR =1.2600 fm; AR =.6300 fm; 9346 1451 120 WD=(3.690+0.400xE) MeV; E< 10 MeV RD =1.24 fm; 9346 1451 121 WD= 7.690 MeV; E>=10 MeV AD =.5200 fm; 9346 1451 122 VSO= 6.2 MeV; RS0=1.12 fm; ASO=.47 fm; 9346 1451 123 B2= .190; B4=.060; 9346 1451 124 9346 1451 125 9346 1451 126 Fission, capture and compound inelastic scattering cross 9346 1451 127 sections were calculated with Hauser-Feshbach-Moldauer /35/ 9346 1451 128 approach, at incident neutron energies higher than 0.515 MeV 9346 1451 129 Tepel et al. /36/ theory was employed. 9346 1451 130 . 9346 1451 131 237-Np level schema as taken from Nuclear Data Sheets/37/. 9346 1451 132 9346 1451 133 NO. ENERGY(MEV) SPIN-PARITY 9346 1451 134 GS 0.0 5/2+ 9346 1451 135 1 0. 331964 7/2+ 9346 1451 136 2 0.0595412 5/2- 9346 1451 137 3 0.07592 9/2+ 9346 1451 138 4 0.10296 7/2- 9346 1451 139 5 0.1300 11/2+ 9346 1451 140 6 0.15851 9/2- 9346 1451 141 7 0.19146 13/2+ 9346 1451 142 8 0.22596 11/2- 9346 1451 143 9 0.26754 3/2- 9346 1451 144 10 0.2699 15/2+ 9346 1451 145 11 0.28135 1/2- 9346 1451 146 12 0.30506 13/2- 9346 1451 147 13 0.32442 7/2- 9346 1451 148 14 0.33236 1/2+ 9346 1451 149 15 0.3485 17/2+ 9346 1451 150 16 0.3597 5/2- 9346 1451 151 17 0.36859 5/2+ 9346 1451 152 18 0.37093 3/2+ 9346 1451 153 19 0.39552 15/2- 9346 1451 154 20 0.43412 11/2- 9346 1451 155 21 0.45253 9/2+ 9346 1451 156 22 0.45400 19/2+ 9346 1451 157 23 0.45969 7/2+ 9346 1451 158 24 0.48596 9/2- 9346 1451 159 25 0.49702 17/2- 9346 1451 160 26 0.51419 3/2- 9346 1451 161 9346 1451 162 9346 1451 163 Continuum levels were assumed above 0.515 MeV 9346 1451 164 9346 1451 165 MT=16,17,37. (n,2n) and (n,3n) cross sections from 9346 1451 166 statistical model calculations with account of 9346 1451 167 pre-equilibrium neutron emission (modified STAPRE code /38/ 9346 1451 168 was used). Pre-equilibrium neutron emission contribution was 9346 1451 169 fixed according to consistent description of (n,F) and (n,xn)9346 1451 170 reaction data for 238-U and 232-Th traget nuclides /13/. 9346 1451 171 In case of 237-Np(n,2n) reaction the yield of short-lived 1- 9346 1451 172 state of 236-Np is measured. The ratio of the yields of short9346 1451 173 -lived (1-) and long-lived(6-) states measured at 14 MeV by 9346 1451 174 Myers et al. /39/ is compatible with calculated cross section9346 1451 175 of 237-Np(n,2n). That means consistent description of 9346 1451 176 data base on fission and 237-Np(n,2n)236-Np(s) is obtained at9346 1451 177 14 MeV. Excited levels of 236-Np are modelled using predicted9346 1451 178 Gallher-Moshkowski doublets by Sood /40/. Modelling of the 9346 1451 179 energy-dependence of the ratio of the yields of short-lived 9346 1451 180 (1-) and long-lived (6-) from threshold energy of (n,2n) up 9346 1451 181 to 20 MeV provides a description of 237-Np(n,2n)236-Np(s) 9346 1451 182 data by Gromova et al. /41/, Nishi et al./42/, Lindner et al.9346 1451 183 /43/, Paulson et al. /44/, Lindeke et al. /45/, Perkin et al.9346 1451 184 /46/ around 14 MeV and Daroczy et al. /47/ data, from 9346 1451 185 (n,2n) threshold up to 10 MeV. 9346 1451 186 9346 1451 187 MT=18, 19, 20, 21,38. Fission cross section is calculated 9346 1451 188 within statistical model /48/. 9346 1451 189 Measured fission data /49-68/ analysis was accomplished 9346 1451 190 witin GMA /5/ approach. Statistical model calculations in 9346 1451 191 the energy of 1 keV-20 MeV are maintained which deviate from 9346 1451 192 the GMA evaluation within GMA-estimated uncertainties 9346 1451 193 The contribution of emissive (n,nf) and (n,2nf) fission to 9346 1451 194 the total fission cross section was calculated using the 9346 1451 195 model /13/, which consistently describes the yield of short- 9346 1451 196 lived state of 236(s)Np in 237-Np(n,2n) reaction, branching 9346 1451 197 ratio of yields of short-lived (1-) and isomer (6-) states 9346 1451 198 236(l)Np/236(l)Np at 14 MeV and measured prompt fission 9346 1451 199 neutron spectrum at 14.7 MeV. Fission probability of 237-Np, 9346 1451 200 fissioning in 237-Np(n,nf) reaction is compatible with 9346 1451 201 236-Np(n,f) data /69,70/ 9346 1451 202 9346 1451 203 MT=102 Capture cross section 9346 1451 204 Capture cross section is calculated within a statistical mo- 9346 1451 205 del. Above neutron energy 5.5 MeV capture cross section is 9346 1451 206 assumed to be 0.001 barn. Competition of (n,gf) and (n,gn') 9346 1451 207 reactions is taken into account. 9346 1451 208 Trend of measured data by Weston and Todd /29/, Eshch et al. 9346 1451 209 /30/,Kobayashi et al. /31/, Lindner et al./43/,Buleeva et al.9346 1451 210 /71/Stupegia et al. /72/, Trofimov et al. /73/ is reproduced.9346 1451 211 9346 1451 212 9346 1451 213 MF=4 Angular distributions of secondary neutrons 9346 1451 214 FOR MT=2,51,53, 55 - from coupled channel calculations 9346 1451 215 (rigid rotator model), with added isotropic compound contri- 9346 1451 216 bution. 9346 1451 217 9346 1451 218 MT=16, 17, 18-21, 38, 52,54,56-76 and 91 are isotropic 9346 1451 219 in the lab. system. 9346 1451 220 9346 1451 221 MF=5 Energy distributions of secondary neutrons 9346 1451 222 9346 1451 223 Energy distributions for MT=16,17,91 were calculated with 9346 1451 224 a Hauser-Feshbach statistical model of cascade neutron 9346 1451 225 emission, taking into account exclusive pre-fission (n,xnf) 9346 1451 226 and (n,xng) neutron spectra, with the allowance of pre-equi- 9346 1451 227 librium emission of first neutron. The calculated spectra are9346 1451 228 strictly correlated with (n,F) and (n,xn) reaction cross 9346 1451 229 sections /13/. 9346 1451 230 9346 1451 231 9346 1451 232 MT=18,19,20,21,38 9346 1451 233 Prompt fission neutron spectra (PFNS) were calculated with 9346 1451 234 phenomenological model /74,13,33/, exclusive pre-fission 9346 1451 235 neutron spectra of(n,xnf) reactions, either equilibrium and 9346 1451 236 Spectra of pre-fission (n,xnf) neutrons are calculated with 9346 1451 237 Hauser-Feshbach statistical model. PFNS from fission frag- 9346 1451 238 ments are calculated as a superposition of two Watt distribu-9346 1451 239 tions for heavy and light fission fragments (FF), the partial9346 1451 240 contributions being equal, while the temperatures different. 9346 1451 241 FF kinetic energy is the superimposed phenomenological para- 9346 1451 242 meter, generally lower, than TKE. That peculiarity roughly 9346 1451 243 reflects its dependence on the moment of prompt fission 9346 1451 244 neutron emission /74/. 9346 1451 245 The model reproduces the shape of PFNS measured at 0.52 MeV 9346 1451 246 by Kornilov et al./19/ and Than Win /, at 5 and 7.8 MeV by 9346 1451 247 Trufanov et al. /76/ and at 2.9 and 14.7 MeV by Boikov et al.9346 1451 248 /11/. Average energies of PFNS predict distinct lowering in 9346 1451 249 the vicinity ov (n,nf) and (n,2nf) reaction thresholds /77/, 9346 1451 250 in general complience with average energies, estimated from 9346 1451 251 the measured PFNS shapes by Taieb et al. /78/. 9346 1451 252 MT=455 9346 1451 253 9346 1451 254 9346 1451 255 9346 1451 256 9346 1451 257 9346 1451 258 MF=9 Multiplicities for Production of Radioactive Nuclides 9346 1451 259 MT=16 9346 1451 260 9346 1451 261 The measured at 14 MeV by Myers et al. /39/ ratio of the 9346 1451 262 yields of long-lived ground state(6-) and short-lived 1- 9346 1451 263 excited (185 keV) states of 236-Np is reproduced. Levels 9346 1451 264 of 236-Np are modelled using predicted Gallher-Moshkowski 9346 1451 265 doublets by Sood /40/. Modelled energy-dependend ratio 9346 1451 266 of the yields of long-lived (6-) and short-lived (1-) from 9346 1451 267 threshold energy of (n,2n) up to 20 MeV describes 9346 1451 268 237-Np(n,2n)236-Np(s)data by Gromova et al. /41/, 9346 1451 269 Nishi et al./42/, Lindner et al. /43/, Paulson et al. /44/, 9346 1451 270 Lindeke et al. /45/, Perkin et al. /46/ around 14 MeV and 9346 1451 271 Daroczy et al. /47/ data, from (n,2n) threshold up to 10 MeV.9346 1451 272 9346 1451 273 Reference 9346 1451 274 9346 1451 275 1. Ignatyuk A.V., Kornilov N.V., Maslov V.M. Isomer ratio and 9346 1451 276 237-Np(n,2n) reaction cross section, Atomnaya Energiya 63, 9346 1451 277 110 (1987). 9346 1451 278 2. Maslov V.M. Analysis of the 237-Np fission cross sections and 9346 1451 279 (n,xn) reactions. INDC(CCP)-366, p. 27, 1994 9346 1451 280 3. 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