40-Zr- 90 JAEA EVAL-Oct18 A.Ichihara DIST-DEC21 20200318 ----JENDL-5 MATERIAL 4025 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2018-10 Evaluated with CCONE code by ichihara 2020-10 Energies of discrete primary photons were corrected. 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF33/MT1-115, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region (MLBW formula) : below 171 keV Resonance parameters for JENDL-3.1 were taken from JENDL-2 after slight modification. For JENDL-2, resonance energies and neutron widths were taken from the data of Musgrove et al./1/ Radiation widths were derived from capture areas measured by Boldeman et al./2/ The parameters of the first resonance were slightly adjusted so as to reproduce the capture and and elastic scattering cross sections at 0.0253 eV/3/. Average radiation width = 0.190 +- 0.110 eV for s-wave res, 0.270 +- 0.120 eV for p-wave res, 0.280 +- 0.120 eV for d-wave res. The effective scattering radius of 7.0 fm was assumed. For JENDL-3, the parameters of three d-wave resonances were modified and a negative resonance was added so as to reproduce the thermal capture cross section of 0.10+-0.07 barn measured by Pomerance/4/, and the resonance integral given by Mughabghab et al./3/ For JENDL-3.2, the parameters for the levels measured by boldeman et al. in the energy range up to 192.9 keV were reevaluated using their capture area data multiplied by 0.967 according to a corrigendum reported by Allen et al./5/. The negative resonance was removed because the positive resonance parameters reproduce well the thermal cross sections/6/ and resonance integral. For JENDL-4.0, the paramters for 3.86 - 68.6 keV were replaced with the ones obtained by Tagliente et al./7/ In JENDL-5, the Reich-Moore (RM) format was applied./7/ The neutron widths of Mughabghab/8/ were adopted for 53.37 and 57.79 keV to reproduce the measured total cross sections of Musgrove et al./1/ The average radiation width 0.25 eV was employed for the s- and d-wave resonances/9/. Unresolved resonance region : 171 keV - 400 keV The unresolved resonance parameters were calculated using the asrep code/10/. 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 5.295 - elastic 5.284 - capture 0.0109 0.164 MF= 3 Neutron cross sections Below 171 keV, resonance parameters were given. Above the energy, cross sections were calculated with the CCONE code /11/. Details of computation are given in /12/. MT= 1 Total cross section Calculated with CCONE code /11/. MT= 2 Elastic scattering cross section Calculated with CCONE code /11/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /11/. MT= 16 (n,2n) cross section Calculated with CCONE code /11/. MT= 22 (n,na) cross section Calculated with CCONE code /11/. MT= 28 (n,np) cross section Calculated with CCONE code /11/. MT=102 Capture cross section Calculated with CCONE code /11/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /11/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /11/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /11/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /11/. MT=111 (n,2p) cross section Calculated with CCONE code /11/. MT=112 (n,pa) cross section Calculated with CCONE code /11/. MT=115 (n,pd) cross section Calculated with CCONE code /11/. MF= 4 Angular distributions of secondary neutrons MT= 2 Elastic scattering Calculated with CCONE code /11/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /11/. MT= 22 (n,na) reaction Calculated with CCONE code /11/. MT= 28 (n,np) reaction Calculated with CCONE code /11/. MT=51-91 (n,n') reaction Calculated with CCONE code /11/. MT=102 Capture reaction Calculated with CCONE code /11/. MT=111 (n,2p) reaction Calculated with CCONE code /11/. MT=112 (n,pa) reaction Calculated with CCONE code /11/. MT=115 (n,pd) reaction Calculated with CCONE code /11/. MT=600-649 (n,p) reaction Calculated with CCONE code /11/. MT=650-699 (n,d) reaction Calculated with CCONE code /11/. MT=700-749 (n,t) reaction Calculated with CCONE code /11/. MT=800-849 (n,a) reaction Calculated with CCONE code /11/. MF= 8 Information on decay data MT=4 (n,n') MT= 16 (n,2n) MT= 22 (n,na) MT= 28 (n,np) MT=102 Capture MT=103 (n,p) MT=104 (n,d) MT=105 (n,t) MT=107 (n,a) MT=111 (n,2p) MT=112 (n,pa) MT=115 (n,pd) MF= 9 Isomeric branching ratios MT=107 (n,a) reaction Calculated with CCONE code /11/. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /11/. MT= 16 (n,2n) reaction Calculated with CCONE code /11/. MT= 28 (n,np) reaction Calculated with CCONE code /11/. MT=103 (n,p) reaction Calculated with CCONE code /11/. MT=104 (n,d) reaction Calculated with CCONE code /11/. MT=112 (n,pa) reaction Calculated with CCONE code /11/. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using KALMAN code and the covariances of model parameters used in the cross-section calculations. Evaluated data with the other methods are described bellow. MT= 1 Total cross section 1.0e-5 eV to 171 keV(RRR): given by a sum of the covariance data of the elastic scattering and the neutron capture cross sections. 171 keV to 20 MeV: obtained by the CCONE-KALMAN. MT= 2 Elastic scattering cross sections 1.0e-5 eV to 171 keV(RRR): obtained by the kernel approximation method. 171 keV to 20 MeV: obtained by the CCONE-KALMAN. MT=102 Capture cross section 1.0e-5 eV to 171 keV(RRR): obtained by the kernel approximation method. 171 keV to 20 MeV: obtained by the CCONE-KALMAN. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /11/ ------------------------------------------------------------------ * Optical model potentials alpha : V.Avrigeanu et al./13/ deuteron: J.M.Lohr and W.Haeberli/14/ He-3 : F.D.Becchetti Jr. and G.W.Greenlees/15/ neutron : S.Kunieda et al./12,16/ proton : S.Kunieda et al./16/ triton : F.D.Becchetti Jr. and G.W.Greenlees/15/ * Level scheme of Zr-90 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.760710 0 + 2 2.186270 2 + 3 2.319000 5 - 4 2.739300 4 - 5 2.747880 3 - 6 3.076930 4 + 7 3.308800 2 + ----------------------- * Level density parameters (Gilbert-Cameron model/17/) Energy dependent parameters of Mengoni-Nakajima/18/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Zr-91 11.890 1.258 -1.233 0.823 0.027 6.228 2.395 Zr-90 11.748 2.530 -1.956 0.791 1.946 6.578 3.309 Zr-89 12.323 1.272 -0.595 0.836 -0.532 7.012 2.151 Y-90 11.500 0.000 -1.297 0.709 -0.368 2.976 1.417 Y-89 11.127 1.272 -1.867 0.694 1.409 3.627 3.248 Y-88 11.495 0.000 -0.510 0.852 -1.643 5.422 0.766 Sr-89 10.953 1.272 -0.952 0.857 0.118 6.194 2.079 Sr-88 11.473 2.558 -1.514 0.826 1.739 7.165 3.585 Sr-87 12.365 1.287 -0.027 0.680 0.465 4.755 1.770 Sr-86 11.308 2.588 0.762 0.854 0.410 8.309 2.230 Rb-86 9.930 0.000 0.003 1.090 -3.244 8.309 0.557 --------------------------------------------------------- * Gamma-ray strength functions for Zr-91 E1: standard lorentzian model(SLO) ER= 16.65 (MeV) EG= 5.59 (MeV) SIG= 183.72 (mb) M1: standard lorentzian model(SLO) ER= 9.12 (MeV) EG= 4.00 (MeV) SIG= 4.23 (mb) E2: standard lorentzian model(SLO) ER= 14.01 (MeV) EG= 5.02 (MeV) SIG= 2.09 (mb) References 1) Musgrove, A.R. de L., et al.: Aust. J. Phys., 30, 379 (1977). 2) Boldeman, J.W., et al.: Nucl. Phys., A246, 1 (1975). 3) Mughabghab, S.F., et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press, New York (1981). 4) Pomerance, H.: Phys. Rev., 88, 412 (1952). 5) Allen, B.J., et al.: Nucl. Sci. Eng., 82, 230 (1982). 6) Lone, M.A. and Bartholomew, G.A.: Proc. 4th Int. Conf. on Neutron-Capture Gamma-Ray Spectroscopy and Related Topics, Grenoble, Sept.1981, p.383 (1981). 7) Taglinte, G., et al.: Phys. Rev., C77, 035802 (2008). 8) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier, Amsterdam (2006). 9) Ichihara, A.: JAEA-Conf 2017-001, 103 (2018). 10) Kikuchi, Y., et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 11) Iwamoto, O.: J. Nucl. Sci. Technol., 44, 687 (2007). 12) Ichihara, A.: J. Nucl. Sci. Technol., 55, 1087 (2018). 13) Avrigeanu, V., et al.: Report OUNP-94-02 (1994) , Phys. Rev., C49, 2136 (1994). 14) Lohr, J.M. and Haeberli, W.: Nucl. Phys., A232, 381 (1974). 15) Becchetti Jr., F.D. and Greenlees, G.W.: Ann. Rept. J.H. Williams Lab., Univ. Minnesota (1969). 16) Kunieda, S., et al.: J. Nucl. Sci. Technol., 44, 838 (2007). 17) Gilbert, A. and Cameron, A.G.W.: Can. J. Phys., 43, 1446 (1965). 18) Mengoni, A. and Nakajima, Y.: J. Nucl. Sci. Technol., 31, 151 (1994).