45-Rh-102MJAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211020 ----JENDL-5 MATERIAL 4523 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-11 (MF3/MT91) QI corrected by N.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 6.45 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.23503E+01 Elastic 5.25436E+00 Inelas 1.98536E-02 1.34541E+00 n,gamma 1.68452E+01 3.42873E+02 n,p 2.96412E-04 6.26184E-03 n,alpha 1.25817E-04 2.56454E-03 ---------------------------------------------------------- (*) 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= 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= 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 2.4eV 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/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering 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= 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=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) 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= 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. MT=111 (n,2p) reaction Decay chain is given in the decay data file. MT=112 (n,pa) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT==102 Capture reaction Calculated with CCONE code /1/. MT=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production reactions MT= 4 (n,n') 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= 24 (n,2na) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./3/ proton : 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 : L.McFadden and G.R.Satchler/7/ * Level scheme of Rh-102 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 2 - 1 0.041940 2 - 2 0.076000 3 - 3 0.105220 3 + 4 0.123750 2 - 5 0.140730 6 + 6 0.154460 5 + 7 0.156490 3 + 8 0.178680 3 + 9 0.206880 2 + 10 0.208740 1 - 11 0.242270 7 + 12 0.259570 2 + 13 0.263840 5 + 14 0.291540 1 - 15 0.297290 7 + 16 0.302220 1 + 17 0.305890 1 - 18 0.345770 2 - 19 0.359100 3 - 20 0.359610 3 - 21 0.364800 1 + 22 0.378610 6 + 23 0.380000 2 - 24 0.399390 6 + 25 0.409910 2 - 26 0.427520 1 - 27 0.431480 5 - 28 0.449360 2 + 29 0.450600 2 - 30 0.474340 5 - 31 0.476850 7 + 32 0.491000 5 - ----------------------- * 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 --------------------------------------------------------- Rh-103 13.507 1.182 2.389 0.711 -1.187 6.395 1.525 Rh-102 13.400 0.000 1.647 0.778 -2.822 6.093 0.491 Rh-101 13.293 1.194 0.877 0.752 -0.937 6.553 1.845 Rh-100 13.186 0.000 0.029 0.887 -3.290 7.558 0.390 Ru-102 13.340 2.376 2.640 0.685 0.275 7.160 2.814 Ru-101 13.841 1.194 2.238 0.733 -1.566 6.917 1.051 Ru-100 13.294 2.400 1.282 0.811 -0.628 8.924 2.666 Ru-99 13.078 1.206 0.664 0.794 -1.207 7.105 1.583 Tc-101 13.293 1.194 3.816 0.694 -1.409 6.373 1.271 Tc-100 13.232 0.000 3.021 0.709 -2.476 5.200 0.552 Tc-99 13.078 1.206 2.475 0.774 -1.773 7.254 1.329 Tc-98 12.971 0.000 1.591 0.766 -2.458 5.621 0.714 Tc-97 12.863 1.218 0.904 0.880 -2.268 8.627 1.380 Tc-96 12.755 0.000 -0.170 0.903 -3.126 7.482 0.656 --------------------------------------------------------- * Gamma-ray strength functions for Rh-103 E1: hybrid model(GH)/10/ ER= 14.31 (MeV) EG= 4.19 (MeV) SIG= 73.19 (mb) ER= 17.29 (MeV) EG= 6.01 (MeV) SIG= 146.39 (mb) M1: standard lorentzian model(SLO) ER= 8.75 (MeV) EG= 4.00 (MeV) SIG= 1.05 (mb) E2: standard lorentzian model(SLO) ER= 13.44 (MeV) EG= 4.87 (MeV) SIG= 2.40 (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) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 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)