42-Mo- 95 JAEA EVAL-MAR09 K.Shibata, A.Ichihara, S.Kunieda+ DIST-MAY10 20091215 ----JENDL-4.0 MATERIAL 4234 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-03 The data above the resolved resonance region were evaluated by K.Shibata, A.Ichihara, and S.Kunieda /1/. The resolved resonance parameters were evaluated by T.Nakagawa. 09-12 Compiled by K.Shibata MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resoannce parameters Resolved resonance region: below 2 keV Based on the experimental data of Shwe et al./2/, Weigmann et al./3/, and Wang et al./4/ Unresolved resonance region: 2 keV - 400 keV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /5/. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 2.0102E+01 Elastic 6.4979E+00 n,gamma 1.3604E+01 1.0181E+02 n,alpha 3.0740E-05 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Sum of partial cross sections. MT= 2 Elastic scattering cross section Originally, the POD calculations were adopted. After considering the benchmark results with molybdenum reflectors for fast neutrons, the data were replaced with the JENDL-3.3 cross sections above 600 keV. MT= 3 Non-elastic cross section Sum of partial nonelastic cross sections MT= 4,51-91 (n,n') cross section Calculated with POD code /5/. MT= 16 (n,2n) cross section Calculated with POD code /5/. MT= 17 (n,3n) cross section Calculated with POD code /5/. MT= 22 (n,na) cross section Calculated with POD code /5/. MT= 28 (n,np) cross section Calculated with POD code /5/. MT= 32 (n,nd) cross section Calculated with POD code /5/. MT=102 Capture cross section Calculated with POD code /5/. MT=103 (n,p) cross section Calculated with POD code /5/. MT=104 (n,d) cross section Calculated with POD code /5/. MT=105 (n,t) cross section Calculated with POD code /5/. MT=106 (n,He3) cross section Calculated with POD code /5/. MT=107 (n,a) cross section Below 2 keV, the cross section was calculated using the resonance parameters given by Rapp et al./6/ The negative resonance parameters were adjusted so as to reproduce the experimental data measured by D'hondt et al./7/. The average cross sections measured by Rapp et al. were used between 2 keV and 500 keV. The cross section was calculated with POD code /5/ above 500 keV. MT=203 (n,xp) cross section Calculated with POD code /5/. MT=204 (n,xd) cross section Calculated with POD code /5/. MT=205 (n,xt) cross section Calculated with POD code /5/. MT=206 (n,xHe3) cross section Calculated with POD code /5/. MT=207 (n,xa) cross section Calculated with POD code /5/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /5/ below 1 MeV. Above 1 MeV, the data were taken from JENDL-3.3 by considering the benchmark results with molybdenum reflectors for fast neutrons. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/5/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/5/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/5/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/5/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/5/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/5/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/5/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/5/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/5/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/5/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/5/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /5/. MF=14 Gamma-ray angular distributions MT= 3 Non-elastic gamma emission Assumed to be isotropic. MF=15 Gamma-ray spectra MT= 3 Non-elastic gamma emission Calculated with POD code /5/.*************************************************************** * Nuclear Model Calculations with POD Code /5/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximaiton (DWBA), one-component exciton preequilibrium model, and the Hauser-Feshbach-Moldauer statis- tical model. With the preequilibrim model, semi-empirical pickup and knockout process can be taken into account for composite-particle emission. The gamma-ray emission from the compound nucleus can be calculated within the framework of the exciton model. The code is capable of reading in particle transmission coefficients calculated by separate spherical or coupled-channel optical model code. 2. Optical model parameters Neutrons: Coupled-channel optical model parameters /8/ Protons: Koning and Delaroche /9/ Deuterons: Lohr and Haeberli /10/ Tritons: Becchetti and Greenlees /11/ He-3: Becchetti and Greenlees /11/ Alphas: Lemos /12/ potentials modified by Arthur and Young /13/ 3. Level scheme of Mo- 95 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 5/2 + 1 0.20412 3/2 + 2 0.76580 7/2 + 3 0.78620 1/2 + 4 0.82063 3/2 + 5 0.94768 9/2 + 6 1.03927 1/2 + 7 1.05676 5/2 + 8 1.07372 7/2 + 9 1.09200 3/2 + 10 1.30259 1/2 + 11 1.32400 3/2 + 12 1.36973 3/2 + 13 1.37601 9/2 + 14 1.42613 5/2 + 15 1.44050 9/2 - 16 1.54079 11/2 + 17 1.55172 9/2 + 18 1.62022 3/2 + 19 1.64510 7/2 + 20 1.66029 3/2 + 21 1.66600 7/2 + 22 1.68300 7/2 + 23 1.69800 1/2 + 24 1.74326 9/2 + 25 1.79666 11/2 + 26 1.80824 7/2 + ------------------------- Levels above 1.81824 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /14/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Mo- 96 13.196 2.449 1.024 0.752 0.273 8.413 2.818 Mo- 95 13.125 1.231 0.096 0.761 -0.609 6.814 1.808 Mo- 94 12.185 2.475 -0.706 0.937 -0.368 10.169 2.853 Mo- 93 12.764 1.244 -1.843 0.892 -0.799 7.716 2.755 Nb- 95 11.759 1.231 1.730 0.720 -0.207 6.109 1.219 Nb- 94 12.820 0.000 0.583 0.682 -1.167 4.340 1.257 Nb- 93 11.549 1.244 0.114 0.953 -1.794 9.243 1.950 Zr- 93 12.411 1.244 0.480 0.758 -0.396 6.546 1.642 Zr- 92 11.702 2.502 -0.002 0.862 0.426 8.855 3.325 Zr- 91 11.895 1.258 -1.229 0.879 -0.489 7.274 3.167 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /15/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) K.Shibata, A.Ichihara, S.Kunieda, J. Nucl. Sci. Technol., 46, 278 (2009). 2) H. Shwe and R.E. Cote, Phys. Rev. 179, 1148 (1969). 3) H. Weigmann, et al., 1971 Knoxville, 749 (1971). 4) T.F. Wang et al., Nucl. Instrum. Meth. Phys. Research B, 266, 561 (2008). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) W. Rapp et al., Phys. Rev., C68, 015802 (2003). 7) D'hondt et al., 1982 Antwerp, 147 (1983). 8) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 9) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 10) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 11) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 12) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 13) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 15) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).