45-Rh-103 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211020 ----JENDL-5 MATERIAL 4525 -----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 MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved resonance parameters Resolved resonance region : below 4.2 keV Resolved resonance parameters were taken from JENDL-4.0. The parameters below 1keV were replaced into those of Brusegan et al./1/. The parameters of negative resonance were modified so as to reproduce the elastic and capture cross sections below 1eV. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.46776E+02 Elastic 4.13670E+00 n,gamma 1.42639E+02 9.65533E+02 n,alpha 3.49060E-10 1.15462E-09 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /2/. MT= 2 Elastic scattering cross section Calculated with CCONE code /2/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /2/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /2/. MT= 16 (n,2n) cross section Calculated with CCONE code /2/. MT= 17 (n,3n) cross section Calculated with CCONE code /2/. MT= 22 (n,na) cross section Calculated with CCONE code /2/. MT= 24 (n,2na) cross section Calculated with CCONE code /2/. MT= 28 (n,np) cross section Calculated with CCONE code /2/. MT= 32 (n,nd) cross section Calculated with CCONE code /2/. MT= 33 (n,nt) cross section Calculated with CCONE code /2/. MT= 41 (n,2np) cross section Calculated with CCONE code /2/. MT=102 Capture cross section Calculated with CCONE code /2/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /2/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /2/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /2/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /2/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /2/. MT=111 (n,2p) cross section Calculated with CCONE code /2/. MT=112 (n,pa) cross section Calculated with CCONE code /2/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT= 24 (n,2na) reaction Calculated with CCONE code /2/. MT= 28 (n,np) reaction Calculated with CCONE code /2/. MT= 32 (n,nd) reaction Calculated with CCONE code /2/. MT= 33 (n,nt) reaction Calculated with CCONE code /2/. MT= 41 (n,2np) reaction Calculated with CCONE code /2/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /2/. MT=102 Capture reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. MT=112 (n,pa) reaction Calculated with CCONE code /2/. MT=600-649 (n,p) reaction Calculated with CCONE code /2/. MT=650-699 (n,d) reaction Calculated with CCONE code /2/. MT=700-749 (n,t) reaction Calculated with CCONE code /2/. MT=750-799 (n,He3) reaction Calculated with CCONE code /2/. MT=800-849 (n,a) reaction Calculated with CCONE code /2/. 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 /2/. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /2/. MT= 16 (n,2n) reaction Calculated with CCONE code /2/. MT= 17 (n,3n) reaction Calculated with CCONE code /2/. MT= 22 (n,na) reaction Calculated with CCONE code /2/. MT=111 (n,2p) reaction Calculated with CCONE code /2/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /2/ ------------------------------------------------------------------ * 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 : F.D.Becchetti Jr. and G.W.Greenlees/6/ He-3 : Y.Xu et al./7/ alpha : L.McFadden and G.R.Satchler/8/ * Level scheme of Rh-103 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 1/2 - 1 0.039750 7/2 + 2 0.093040 9/2 + 3 0.294960 3/2 - 4 0.357400 5/2 - 5 0.536840 5/2 + 6 0.607410 5/2 + 7 0.650060 5/2 + 8 0.651720 3/2 + 9 0.657760 11/2 + 10 0.781150 9/2 + 11 0.803160 1/2 - 12 0.821450 13/2 + 13 0.847590 7/2 - 14 0.880460 5/2 - 15 0.903200 11/2 + 16 0.920090 9/2 - 17 1.078310 7/2 + 18 1.106860 5/2 - 19 1.135800 1/2 - 20 1.252100 5/2 + 21 1.256500 3/2 - 22 1.277170 3/2 - 23 1.293990 3/2 - 24 1.327000 11/2 - 25 1.344700 9/2 + 26 1.349500 13/2 + 27 1.404000 5/2 - 28 1.410930 5/2 - 29 1.411060 3/2 - 30 1.420500 1/2 + 31 1.428700 7/2 + 32 1.438400 3/2 + 33 1.443630 1/2 - 34 1.466400 3/2 - 35 1.470000 3/2 + 36 1.480100 11/2 - 37 1.482360 5/2 + 38 1.491600 5/2 - 39 1.515600 5/2 - 40 1.524700 15/2 + ----------------------- * 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-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 Rh-101 13.293 1.194 0.877 0.752 -0.937 6.553 1.845 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 Ru-100 13.294 2.400 1.282 0.811 -0.628 8.924 2.666 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 Tc-97 12.863 1.218 0.904 0.880 -2.268 8.627 1.380 --------------------------------------------------------- * Gamma-ray strength functions for Rh-104 E1: hybrid model(GH)/11/ ER= 14.09 (MeV) EG= 4.07 (MeV) SIG= 74.06 (mb) ER= 17.39 (MeV) EG= 6.08 (MeV) SIG= 148.12 (mb) M1: standard lorentzian model(SLO) ER= 8.72 (MeV) EG= 4.00 (MeV) SIG= 1.05 (mb) E2: standard lorentzian model(SLO) ER= 13.40 (MeV) EG= 4.86 (MeV) SIG= 2.38 (mb) References 1) A.Brusegan et al., Int. Conf. on Nuclear Data for Science and Technology, 953 (2005) 2) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 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) F.D.Becchetti Jr. and G.W.Greenlees, Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969) 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)