92-U -240 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210920 ----JENDL-5 MATERIAL 9243 -----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 8.44 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 9.43040E+00 Elastic 8.97876E+00 Fission 3.23639E-04 1.44139E-02 n,gamma 4.03340E-01 1.80980E+01 n,alpha 2.38340E-15 1.06680E-13 ---------------------------------------------------------- (*) 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=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 16.47 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= 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=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. ------------------------------------------------------------------ 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 U-240 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.045000 2 + 2 0.150600 4 + 3 0.313190 6 + 4 0.528690 8 + 5 0.792900 10 + 6 0.847000 3 - 7 0.944700 5 - 8 1.040000 0 + ----------------------- * 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 --------------------------------------------------------- U-241 27.255 0.773 3.365 0.382 -0.763 4.153 0.000 U-240 27.161 1.549 3.321 0.340 0.560 4.127 1.040 U-239 27.546 0.776 3.076 0.360 -0.452 3.717 0.498 U-238 27.174 1.556 3.011 0.395 -0.086 5.121 1.504 U-237 27.165 0.779 2.744 0.386 -0.679 4.109 0.971 Pa-240 27.161 0.000 3.924 0.378 -1.577 3.384 0.000 Pa-239 27.066 0.776 3.991 0.379 -0.807 4.165 0.000 Pa-238 26.971 0.000 3.646 0.383 -1.561 3.393 0.000 Pa-237 26.876 0.779 3.683 0.301 0.181 2.712 0.686 Pa-236 26.781 0.000 3.343 0.318 -0.720 2.160 0.032 Th-239 27.066 0.776 4.273 0.376 -0.827 4.165 0.000 Th-238 26.971 1.556 4.194 0.378 -0.044 4.949 0.000 Th-237 26.876 0.779 3.926 0.381 -0.803 4.177 0.000 Th-236 26.781 1.562 3.837 0.383 -0.016 4.964 0.000 Th-235 26.686 0.783 3.658 0.385 -0.784 4.189 0.000 Th-234 26.591 1.569 3.625 0.334 0.660 4.010 0.995 Th-233 27.374 0.786 3.553 0.376 -0.736 4.101 0.830 Th-232 26.401 1.576 3.394 0.408 -0.213 5.329 1.293 --------------------------------------------------------- * Gamma-ray strength functions for U-241 E1: hybrid model(GH)/10/ ER= 11.46 (MeV) EG= 2.74 (MeV) SIG= 239.70 (mb) ER= 14.40 (MeV) EG= 4.24 (MeV) SIG= 479.41 (mb) M1: standard lorentzian model(SLO) ER= 6.59 (MeV) EG= 4.00 (MeV) SIG= 1.44 (mb) E2: standard lorentzian model(SLO) ER= 10.12 (MeV) EG= 3.22 (MeV) SIG= 6.50 (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)