40-Zr- 96 EVAL-Oct18 ichihara DIST-DEC21 20200318 ----JENDL-5 MATERIAL 4043 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-10 Evaluated with CCONE code by ichihara 2020-10 Energies of discrete primary photons were corrected. 2021-10 Themal capture cross section adjusted by N.Iwamoto 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region: below 100 keV In JENDL-3.3, resonance energies and neutron widths were based on the measured values by Coceva et al./1/ below 41.5 keV and those by Musgrove et al./2/ above 41.5 keV. The neutron widths of Musgrove et al. were multiplied by a factor of 1.79 so as to be consistent with the data of Coceva et al. The radiation widths were adopted from Brusegan et al./3/ The parameters of the 301-eV level were taken from Salah et al./4/ Parameter of a negative resonance was based on the recommended parameters given in ref./5/, and the radiation width was modified so as to reproduce the capture cross section of 0.0229+-0.0010 barns at 0.0253 eV/5/. Average radiation widths of 0.068+-0.010 eV and 0.170+-0.130 eV were adopted to s-wave and p-wave resonances, respectively. In JENDL-4.0, the parameters of Er=301.1eV(p-wave) resonance of JENDL-3.3 was replaced by those of Er=301.1eV resonance measured by Leinweber et al./6/. Neutron width and capture width of the resonance were somewhat modified within the experimental error, to obtain better agreement with the capture resonance integral value given by Mughabghab/7/. Negative resonance capture width was adjusted to reproduce 2200m/s capture cross section given by Mughabghab/7/. In JENDL-5, the Reich-Moore (RM) format was employed. /8/ The radiation widths below 37 keV were replaced with the data measured by Tagliente et al./8/ The scattering radius of 6.8 fm was applied./7,8/ The recommended data of Mughabghab/9/ were adopted for the negative resonance. The average radiation widths of 0.08 eV and 0.13 eV were applied for the s-wave and p-wave resonances./10/ Thermal capture cross section was reproduced by adjusting the parameter of negative resonance. Unresolved resonance region : 100 keV - 300 keV The unresolved resonance parameters were calculated using the asrep code/11/. The parameters should be used only for the self-shielding calculation. calculated 2200-m/s cross sections and res. integrals (barns) 2200 m/s res. integ. total 5.626 - elastic 5.605 - capture 0.02096 5.36 MF= 3 Neutron cross sections Below 100 keV, resonance parameters were given. Above the energy, cross sections were calculated with the CCONE code /12/. Details of computation are given in /13/. MT= 1 Total cross section Calculated with CCONE code /12/. MT= 2 Elastic scattering cross section Calculated with CCONE code /12/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /12/. MT= 16 (n,2n) cross section Calculated with CCONE code /12/. MT= 17 (n,3n) cross section Calculated with CCONE code /12/. MT= 22 (n,na) cross section Calculated with CCONE code /12/. MT= 24 (n,2na) cross section Calculated with CCONE code /12/. MT= 28 (n,np) cross section Calculated with CCONE code /12/. MT= 32 (n,nd) cross section Calculated with CCONE code /12/. MT=102 Capture cross section Calculated with CCONE code /12/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /12/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /12/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /12/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /12/. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /12/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /12/. MT= 17 (n,3n) reaction Calculated with CCONE code /12/. MT= 22 (n,na) reaction Calculated with CCONE code /12/. MT= 24 (n,2na) reaction Calculated with CCONE code /12/. MT= 28 (n,np) reaction Calculated with CCONE code /12/. MT= 32 (n,nd) reaction Calculated with CCONE code /12/. MT=51-91 (n,n') reaction Calculated with CCONE code /12/. MT=102 Capture reaction Calculated with CCONE code /12/. MT=600-649 (n,p) reaction Calculated with CCONE code /12/. MT=650-699 (n,d) reaction Calculated with CCONE code /12/. MT=700-749 (n,t) reaction Calculated with CCONE code /12/. MT=800-849 (n,a) reaction Calculated with CCONE code /12/. MF= 8 Information on decay data MT=4 (n,n') MT= 16 (n,2n) MT= 17 (n,3n) MT= 22 (n,na) MT= 24 (n,2na) MT= 28 (n,np) MT= 32 (n,nd) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=107 (n,a) ------------------------------------------------------------------ nuclear model calculation with CCONE code /12/ ------------------------------------------------------------------ * Optical model potentials alpha : V.Avrigeanu et al./14/ deuteron: J.M.Lohr and W.Haeberli/15/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/16/ neutron : S.Kunieda et al./13,17/ proton : S.Kunieda et al./17/ triton : F.D.Becchetti Jr. and G.W.Greenlees/16/ * Level scheme of Zr-96 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.581640 0 + 2 1.750500 2 + 3 1.897160 3 - ----------------------- * Level density parameters (Gilbert-Cameron model/18/) Energy dependent parameters of Mengoni-Nakajima/19/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Zr-97 12.181 1.218 2.501 0.588 0.448 4.106 1.400 Zr-96 12.403 2.449 2.144 0.706 0.688 6.950 1.897 Zr-95 11.637 1.231 1.508 0.728 -0.039 5.469 2.372 Zr-94 12.185 2.475 1.414 0.767 0.469 7.586 2.151 Y-96 12.360 0.000 2.855 0.497 -0.313 1.958 0.932 Y-95 11.759 1.231 2.582 0.476 1.182 2.752 2.021 Y-94 13.100 0.000 1.472 0.385 0.207 0.774 0.724 Sr-93 12.762 1.244 1.857 0.620 0.180 4.623 1.238 Sr-92 11.967 2.502 1.541 0.747 0.736 7.218 2.088 Sr-91 12.543 1.258 0.607 0.671 0.243 4.893 1.368 --------------------------------------------------------- * Gamma-ray strength functions for Zr-97 E1: standard lorentzian model(SLO) ER= 13.87 (MeV) EG= 3.95 (MeV) SIG= 66.09 (mb) ER= 18.04 (MeV) EG= 6.52 (MeV) SIG= 132.17 (mb) M1: standard lorentzian model(SLO) ER= 8.92 (MeV) EG= 4.00 (MeV) SIG= 3.95 (mb) E2: standard lorentzian model(SLO) ER= 13.71 (MeV) EG= 4.95 (MeV) SIG= 1.99 (mb) References 1) Coceva, C., et al.: "Proc. Int. Conf. on Nuclear Cross Sections for Technology, Knoxville 1979", 319 (1980). 2) Musgrove, A.R. de L.: et al.: AAEC/E-415 (1977). 3) Brusegan, A., et al.: "Proc. 4th Int. Symp. on Neutron-Capture Gamma-Ray Spectroscopy and Related Topics, Grenoble 1981", 406, Institute of Physics, London (1982). 4) Salah, M.M., et al.: "Proc. Int. Conf. on Nuclear Data for Basic and Applied Science, Santa Fe 1985", Vol. 1, 593 (1986). 5) Mughabghab, S.F., et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press, New York (1981). 6) Leinweber, G., et al.: Nucl. Sci. Eng., 134, 50 (2000). 7) Mughabghab, S.F.: "Atlas of Neutron Resonances, 5th Edition", Elsevier, Amsterdam (2006). 8) Tagliente, G., et al.: Phys. Rev., C84, 055802 (2011). 9) Mughabghab, S.F.: "Atlas of Neutron Resonances, 6th Edition, Vol. 1", Elsevier, Amsterdam (2018). 10) Ichihara, A.: JAEA-Conf 2017-001, 103 (2018). 11) Kikuchi, Y., et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 12) Iwamoto, O.: J. Nucl. Sci. Technol., 44, 687 (2007). 13) Ichihara, A.: J. Nucl. Sci. Technol., 55, 1087 (2018). 14) Avrigeanu, V., et al.: Report OUNP-94-02 (1994) , Phys. Rev., C49, 2136 (1994). 15) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974). 16) Becchetti Jr., F.D. and Greenlees, G.W.: Ann. Rept. J.H. Williams Lab., Univ. Minnesota (1969). 17) Kunieda, S., et al.: J. Nucl. Sci. Technol., 44, 838 (2007). 18) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446 (1965). 19) Mengoni, A. and Nakajima, Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 1 451 361 1