82-Pb-206 EVAL-Feb21 niwamoto DIST-DEC21 20210228 ----JENDL-5 MATERIAL 8231 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 20-01 Evaluated with CCONE code by N.Iwamoto 20-10 Energies of discrete primary photons were corrected by N.Iwamoto. 21-02 Thermal capture cross section was adjusted by N.Iwamoto. 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF33/MT1-107, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonances Resolved resonance parameters (below 820 keV) Data taken from JENDL-4.0 The gamma widths of the negative resonances were adjusted to reproduce the data of Schillebeeckx et al./1/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 1.08781E+01 Elastic 1.08491E+01 n,gamma 2.89653E-02 9.19460E-02 n,alpha 6.46430E-10 9.59456E-08 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Based on experimental data/2,3/ and CCONE calculation/4/. MT= 2 Elastic scattering cross section Calculated with CCONE code /4/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /4/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /4/. MT= 16 (n,2n) cross section Calculated with CCONE code /4/. MT= 17 (n,3n) cross section Calculated with CCONE code /4/. MT= 22 (n,na) cross section Calculated with CCONE code /4/. MT= 28 (n,np) cross section Calculated with CCONE code /4/. MT= 32 (n,nd) cross section Calculated with CCONE code /4/. MT=102 Capture cross section Calculated with CCONE code /4/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /4/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /4/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /4/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /4/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /4/. Below 820 keV the cross section of histogram form was taken from JENDL-4.0. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /4/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /4/. MT= 16 (n,2n) reaction Calculated with CCONE code /4/. MT= 17 (n,3n) reaction Calculated with CCONE code /4/. MT= 22 (n,na) reaction Calculated with CCONE code /4/. MT= 28 (n,np) reaction Calculated with CCONE code /4/. MT= 32 (n,nd) reaction Calculated with CCONE code /4/. MT=51-91 (n,n') reaction Calculated with CCONE code /4/. MT=102 Capture reaction Calculated with CCONE code /4/. MT=600-649 (n,p) reaction Calculated with CCONE code /4/. MT=650-699 (n,d) reaction Calculated with CCONE code /4/. MT=700-749 (n,t) reaction Calculated with CCONE code /4/. MT=750-799 (n,He3) reaction Calculated with CCONE code /4/. MT=800-849 (n,a) reaction Calculated with CCONE code /4/. 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=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 /4/. MF=10 Nuclide production cross sections MT= 17 (n,3n) reaction Calculated with CCONE code /4/. MF=33 Covariances of neutron cross sections Covariances were given to all the cross sections by using KALMAN code and the covariances of model parameters used in the cross-section calculations. Evaluated data with the other methods are described bellow. MT= 1 Total cross section 1.0e-5 eV to 820 keV(RRR): given by a sum of the covariance data of the elastic scattering and the neutron capture cross sections. 820 keV to 5.5 MeV: obtained based on the average cross section of the experimental data. 5.5 MeV to 20 MeV: obtained by the CCONE-KALMAN. MT= 2 Elastic scattering cross sections 1.0e-5 eV to 820 keV(RRR): obtained by the kernel approximation method. 820 keV to 20 MeV: obtained by the CCONE-KALMAN. MT=102 Capture cross section 1.0e-5 eV to 820 keV(RRR): obtained by the kernel approximation method. 820 keV to 20 MeV: obtained by the CCONE-KALMAN. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /4/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning et al./7/ proton : global OMP, A.J.Koning and J.P.Delaroche/8/ modified deuteron: folding OMP, A.J.Koning and J.P.Delaroche/8/ triton : folding OMP, A.J.Koning and J.P.Delaroche/8/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/8/ alpha : L.McFadden and G.R.Satchler/9/ modified * Level scheme of Pb-206 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.803050 2 + 2 1.166400 0 + 3 1.340490 3 + 4 1.466810 2 + 5 1.683990 4 + 6 1.704450 1 + 7 1.784090 2 + 8 1.997670 4 + 9 2.148970 2 + 10 2.196700 3 + 11 2.200160 7 - 12 2.236530 1 - 13 2.314000 0 + 14 2.384150 6 - 15 2.391340 4 - 16 2.423360 2 + 17 2.647800 3 - 18 2.658320 9 - 19 2.782170 5 - 20 2.826310 4 + 21 2.864550 7 - 22 2.929090 4 + 23 2.939600 6 - 24 2.954500 8 - 25 2.960000 4 - 26 2.984000 2 + 27 3.016430 5 - 28 3.033000 2 - 29 3.122380 3 + 30 3.139000 2 - 31 3.194000 5 - 32 3.194300 1 + 33 3.225400 5 - 34 3.244240 4 - 35 3.260400 6 + 36 3.279210 5 - ----------------------- * Gamma-ray strength functions for Pb-207 E1: enhanced generalized lorentzian model(EGLO)/10/ ER= 13.74 (MeV) EG= 3.88 (MeV) SIG= 585.51 (mb) M1: standard lorentzian model(SLO) ER= 6.93 (MeV) EG= 4.00 (MeV) SIG= 0.90 (mb) E2: standard lorentzian model(SLO) ER= 10.65 (MeV) EG= 3.63 (MeV) SIG= 5.33 (mb) References 1) P.Schillebeeckx et al. Eur. Phys. J. A49, 143 (2013). 2) D.J.Horen et al.: Phys Rev. C20, 478 (1979). 3) D.G.Foster Jr, D.W.Glasgow: Phys. Rev. C3, 576 (1971). 4) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007). 5) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in Japanese. 6) P.Oblozinsky et al.: NL-91287-2010 (2010). 7) A.J.Koning et al., Nucl. Sci. Eng., 156, 357 (2007). 8) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 9) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966). 10) J. Kopecky et al., Phys. Rev. C 47, 312 (1993).