45-Rh-104 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211020 ----JENDL-5 MATERIAL 4528 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 Evaluated with CCONE code 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 4.55536E+01 Elastic 5.25385E+00 n,gamma 4.00154E+01 3.36217E+02 n,p 5.67241E-04 4.67457E-03 n,alpha 7.59601E-07 6.37888E-06 ---------------------------------------------------------- (*) 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 obtained from Roy/2,3/. Below 2.6eV 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/. 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=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. MF= 9 Isomeric branching ratios MT==102 Capture 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/. 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./4/ proton : A.J.Koning and J.P.Delaroche/5/ deuteron: Y.Han et al./6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : Y.Xu et al./7/ alpha : L.McFadden and G.R.Satchler/8/ * Level scheme of Rh-104 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1 + 1 0.051420 2 - 2 0.097100 2 + 3 0.128970 5 + 4 0.175240 6 + 5 0.180840 1 + 6 0.186040 1 - 7 0.197890 2 + 8 0.213060 1 + 9 0.224420 2 + 10 0.266770 2 - 11 0.269270 3 - 12 0.329800 2 + 13 0.344590 6 - 14 0.349610 6 + 15 0.358630 1 + 16 0.363180 3 + 17 0.380530 5 - 18 0.384990 1 - 19 0.394190 7 - 20 0.394760 3 + 21 0.400760 2 + 22 0.404510 2 - 23 0.406900 4 + 24 0.416240 7 + 25 0.420770 1 + 26 0.426360 3 - 27 0.455490 8 - 28 0.459640 1 - 29 0.465890 4 - 30 0.482330 2 + 31 0.486190 4 + 32 0.498050 2 + 33 0.505190 2 - 34 0.514520 2 - 35 0.521950 1 - 36 0.524700 1 + 37 0.537740 1 + 38 0.552300 9 - ----------------------- * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Rh-105 13.720 1.171 3.416 0.698 -1.518 6.540 1.019 Rh-104 13.378 0.000 2.963 0.709 -2.489 5.256 0.552 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 Ru-104 13.613 2.353 3.620 0.639 0.332 6.789 2.630 Ru-103 14.179 1.182 3.534 0.703 -1.851 6.880 0.775 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 Tc-103 13.507 1.182 4.667 0.663 -1.419 6.175 0.779 Tc-102 13.400 0.000 4.206 0.578 -1.483 3.587 0.443 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 --------------------------------------------------------- * Gamma-ray strength functions for Rh-105 E1: hybrid model(GH)/11/ ER= 14.06 (MeV) EG= 4.05 (MeV) SIG= 74.92 (mb) ER= 17.35 (MeV) EG= 6.05 (MeV) SIG= 149.84 (mb) M1: standard lorentzian model(SLO) ER= 8.69 (MeV) EG= 4.00 (MeV) SIG= 1.04 (mb) E2: standard lorentzian model(SLO) ER= 13.35 (MeV) EG= 4.85 (MeV) SIG= 2.37 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) J.C.Roy, AECL Chalk River Reports, No.15, p.10 (1958) 3) J.C.Roy, AECL Chalk River Reports, No.14, p.12 (1958) 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 8) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 9) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 10) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 11) S.Goriely, Phys. Lett. B436, 10 (1998)