77-Ir-193 JAEA EVAL-Oct21 N.Iwamoto DIST-DEC21 20211029 ----JENDL-5 MATERIAL 7731 -----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 233 eV Resolved resonance parameters were taken from Mughabghab /1/. The parameters of the first level (1.3047eV) were evaluated from Vertebnyj et al./2/, Fischer et al. /3/ and Masyanov/4/. If the total spin J of resonance level was not known, it was determined from the spin distribution of the level density randomly. The negative resonance was placed so as to reproduce the cross sections at thermal energy recommended by Mughabghab /1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.23035E+02 Elastic 1.19956E+01 n,gamma 1.11039E+02 1.32180E+03 n,alpha 2.17550E-11 3.39496E-10 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /5/. MT= 2 Elastic scattering cross section Calculated with CCONE code /5/. MT= 4,51-91 (n,n') cross section Calculated with CCONE code /5/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /5/. MT= 16 (n,2n) cross section Calculated with CCONE code /5/. MT= 17 (n,3n) cross section Calculated with CCONE code /5/. MT= 22 (n,na) cross section Calculated with CCONE code /5/. MT= 28 (n,np) cross section Calculated with CCONE code /5/. MT= 32 (n,nd) cross section Calculated with CCONE code /5/. MT= 33 (n,nt) cross section Calculated with CCONE code /5/. MT= 41 (n,2np) cross section Calculated with CCONE code /5/. MT=102 Capture cross section Calculated with CCONE code /5/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /5/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /5/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /5/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /5/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /5/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /5/. MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 17 (n,3n) reaction Calculated with CCONE code /5/. MT= 22 (n,na) reaction Calculated with CCONE code /5/. MT= 28 (n,np) reaction Calculated with CCONE code /5/. MT= 32 (n,nd) reaction Calculated with CCONE code /5/. MT= 33 (n,nt) reaction Calculated with CCONE code /5/. MT= 41 (n,2np) reaction Calculated with CCONE code /5/. MT= 51- 91 (n,n') reaction Calculated with CCONE code /5/. MT=102 Capture reaction Calculated with CCONE code /5/. MT=600-649 (n,p) reaction Calculated with CCONE code /5/. MT=650-699 (n,d) reaction Calculated with CCONE code /5/. MT=700-749 (n,t) reaction Calculated with CCONE code /5/. MT=750-799 (n,He3) reaction Calculated with CCONE code /5/. MT=800-849 (n,a) reaction Calculated with CCONE code /5/. 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= 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 /5/. MT=107 (n,a) reaction Calculated with CCONE code /5/. MF=10 Nuclide production reactions MT= 4 (n,n') reaction Calculated with CCONE code /5/. MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 17 (n,3n) reaction Calculated with CCONE code /5/. MT= 32 (n,nd) reaction Calculated with CCONE code /5/. MT= 33 (n,nt) reaction Calculated with CCONE code /5/. MT= 41 (n,2np) reaction Calculated with CCONE code /5/. MT=105 (n,t) reaction Calculated with CCONE code /5/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /5/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./6/ proton : A.J.Koning and J.P.Delaroche/7/ deuteron: Y.Han et al./8/ triton : folding OMP, A.J.Koning and J.P.Delaroche/7/ He-3 : Y.Xu et al./9/ alpha : L.McFadden and G.R.Satchler/10/ * Level scheme of Ir-193 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 3/2 + 1 0.073040 1/2 + 2 0.080240 11/2 - 3 0.138940 5/2 + 4 0.180070 3/2 + 5 0.299400 7/2 - 6 0.357770 7/2 + 7 0.361860 5/2 + 8 0.460540 3/2 + 9 0.469390 13/2 - 10 0.478990 15/2 - 11 0.516410 7/2 + 12 0.521920 9/2 + 13 0.557450 1/2 + 14 0.559300 5/2 + 15 0.563400 9/2 - 16 0.598230 3/2 - 17 0.620990 7/2 + 18 0.695130 5/2 + 19 0.712170 3/2 + 20 0.740380 5/2 - 21 0.806900 5/2 + 22 0.828920 9/2 - 23 0.832900 11/2 - 24 0.838920 9/2 + 25 0.848930 5/2 + 26 0.849080 3/2 + 27 0.857030 11/2 + 28 0.874290 3/2 + 29 0.892270 9/2 + 30 0.918360 7/2 - 31 0.930430 17/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/11/) Energy dependent parameters of Mengoni-Nakajima/12/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ir-194 23.564 0.000 -1.010 0.518 -1.667 4.407 0.436 Ir-193 23.681 0.864 -0.504 0.512 -0.920 5.320 0.930 Ir-192 23.376 0.000 -0.033 0.521 -1.981 4.678 0.332 Ir-191 22.448 0.868 0.292 0.510 -0.867 5.167 1.070 Os-193 24.392 0.864 -0.620 0.494 -0.792 5.082 0.545 Os-192 22.546 1.732 -0.346 0.529 -0.069 6.276 1.465 Os-191 23.607 0.868 0.160 0.527 -1.323 5.799 0.762 Os-190 22.771 1.741 0.301 0.509 -0.056 6.103 1.836 Os-189 23.040 0.873 0.719 0.518 -1.233 5.586 0.736 Re-192 22.546 0.000 0.341 0.376 -0.401 2.017 0.267 Re-191 22.448 0.868 0.590 0.508 -0.923 5.191 0.627 Re-190 22.351 0.000 0.569 0.396 -0.577 2.324 0.210 Re-189 22.253 0.873 0.930 0.475 -0.567 4.592 0.697 Re-188 21.703 0.000 0.838 0.480 -1.369 3.665 0.575 Re-187 22.057 0.878 1.028 0.499 -0.842 5.020 1.043 Re-186 21.080 0.000 0.935 0.471 -1.173 3.378 0.689 --------------------------------------------------------- * Gamma-ray strength functions for Ir-194 E1: hybrid model(GH)/13/ ER= 12.66 (MeV) EG= 3.31 (MeV) SIG= 177.87 (mb) ER= 14.69 (MeV) EG= 4.41 (MeV) SIG= 355.74 (mb) M1: standard lorentzian model(SLO) ER= 7.08 (MeV) EG= 4.00 (MeV) SIG= 1.05 (mb) E2: standard lorentzian model(SLO) ER= 10.88 (MeV) EG= 3.78 (MeV) SIG= 4.81 (mb) References 1) S.F.Mughabghab, Atlas of Neutron Resonances (2006) 2) V.P.Vertebnyj et al., Proc. of 5th All-Union Conference on Neutron Physics, Vol.2, p.114 3) P.Fischer et al., Ges. Kernen.-Verwertung, Schiffbau and Schiffahrt, No.81/E/17 (1981) 4) S.M.Masyanov et al., Atomnaya Energiya, 73, 164 (1992) 5) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 7) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 8) Y.Han et al., Phys. Rev. C 74,044615(2006) 9) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 10) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 11) A.Gilbert and A.G.W.Cameron, Can. J. Phys, 43, 1446 (1965) 12) A.Mengoni and Y.Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 13) S.Goriely, Phys. Lett. B436, 10 (1998)