97-Bk-248MJAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 9750 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code by N.Iwamoto 21-11 JENDL-5rc1 revised by N.Iwamoto (MF1/MT452,456) added (MF4,5/MT18) converted from (MF6/MT18) and added 21-12 JENDL-5rc1 revised by N.Iwamoto (MF5/MT18) corrected 21-12 (MF8/MT18) added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MT=452 Number of Neutrons per fission MT=456 Number of prompt neutrons per fission MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 8.53 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 8.10806E+01 Elastic 9.15767E+00 Fission 5.39827E+00 2.19098E+01 n,gamma 6.62011E+01 2.71215E+02 n,p 2.88040E-18 1.23922E-17 n,alpha 7.93984E-09 3.29833E-08 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/. MT= 2 Elastic scattering cross section Calculated with CCONE code /1/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 18 Fission cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 24 (n,2na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 33 (n,nt) cross section Calculated with CCONE code /1/. MT= 37 (n,4n) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 1.00 eV the 1/v cross section was assumed. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MT= 18 Fission reaction Isotropic distributions in the laboratory system were assumed. MF= 5 Energy distributions of secondary neutrons MT= 18 Prompt neutrons Calculated with CCONE code/1/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 24 (n,2na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 37 (n,4n) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 5 Total reaction (except fission) reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 24 (n,2na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 33 (n,nt) reaction Decay chain is given in the decay data file. MT= 37 (n,4n) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT= 22 (n,na) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT=106 (n,He3) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : global OMP, A.J.Koning and J.P.Delaroche/4/ deuteron: Y.Han et al./5/ triton : folding OMP, A.J.Koning and J.P.Delaroche/4/ He-3 : Y.Xu et al./6/ alpha : M.Avrigeanu and V.Avrigeanu/7/ * Level scheme of Bk-248 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 6 + 1 0.030000 1 - ----------------------- * Level density parameters (Gilbert-Cameron model/8/) Energy dependent parameters of Mengoni-Nakajima/9/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Bk-249 28.012 0.760 1.621 0.402 -0.784 4.334 0.794 Bk-248 27.917 0.000 1.244 0.352 -0.851 2.539 0.030 Bk-247 27.823 0.764 1.318 0.374 -0.338 3.700 0.587 Bk-246 27.728 0.000 0.939 0.400 -1.338 3.358 0.000 Bk-245 27.634 0.767 1.207 0.399 -0.595 4.129 1.560 Cm-248 27.564 1.524 2.051 0.370 0.366 4.483 1.547 Cm-247 26.808 0.764 1.779 0.397 -0.576 4.071 0.749 Cm-246 28.090 1.530 1.729 0.394 0.048 4.987 1.452 Cm-245 27.591 0.767 1.460 0.393 -0.567 4.056 0.891 Cm-244 27.629 1.536 1.533 0.479 -1.135 6.744 0.043 Am-247 27.823 0.764 2.859 0.381 -0.727 4.118 0.000 Am-246 27.728 0.000 2.483 0.327 -0.765 2.283 0.030 Am-245 27.634 0.767 2.456 0.293 0.330 2.497 0.958 Am-244 26.503 0.000 1.975 0.328 -0.587 2.084 0.857 Am-243 28.733 0.770 2.097 0.372 -0.579 3.945 0.532 Am-242 26.639 0.000 1.683 0.338 -0.651 2.209 0.865 Am-241 27.255 0.773 1.731 0.386 -0.495 3.937 0.822 Am-240 27.161 0.000 1.346 0.402 -1.378 3.384 0.757 --------------------------------------------------------- * Gamma-ray strength functions for Bk-249 E1: hybrid model(GH)/10/ ER= 11.29 (MeV) EG= 2.66 (MeV) SIG= 253.14 (mb) ER= 14.36 (MeV) EG= 4.22 (MeV) SIG= 506.27 (mb) M1: standard lorentzian model(SLO) ER= 6.52 (MeV) EG= 4.00 (MeV) SIG= 1.54 (mb) E2: standard lorentzian model(SLO) ER= 10.01 (MeV) EG= 3.12 (MeV) SIG= 7.21 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 4) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 5) Y.Han et al., Phys. Rev. C 74,044615(2006) 6) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 7) M.Avrigeanu and V.Avrigeanu, Phys. Rev. C82, 014606 (2010) 8) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 9) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 10) S.Goriely, Phys. Lett. B436, 10 (1998)