22-Ti- 48 JAEA EVAL-Aug21 N.Iwamoto DIST-DEC21 20210820 ----JENDL-5 MATERIAL 2231 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-08 Evaluated with CCONE code by N.Iwamoto 21-10 Secondary energy grids were revised below 100keV by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF32/MT151) Added (MF33/MT1-111, MF34/MT2) Evaluated with CCONE-KALMAN MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved resonance parameters Resonance parameters were taken from ENDF/B-VIII.0/#b8/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 1.23575E+01 Elastic 4.03899E+00 n,gamma 8.31790E+00 3.77241E+00 ---------------------------------------------------------- (*) 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= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. 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/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. The Legendre coefficients were replaced into the data of Barnard et al./2/ in the energy ranges of 0.3 to 1.5MeV. The Legendre coefficients were derived by the data of Guenther et al./3/ in the energy ranges of 1.5 to 3.8MeV. 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= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) 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=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= 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=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. MF=10 Nuclide production cross sections MT=4 (n,n') reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MF=32 Covariances of resonance parameters MT=151 Resonance parameters Data were taken from ENDF-B-VIII.0. 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. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Covariances were given only to P1 components. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : local OMP, A.J.Koning and J.P.Delaroche/4/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/4/ modified 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/ modified * Level scheme of Ti-48 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.983540 2 + 2 2.295650 4 + 3 2.421060 2 + 4 2.465000 4 - 5 2.997220 0 + 6 3.062000 2 + 7 3.223980 3 + 8 3.239780 4 + 9 3.333200 6 + 10 3.358830 3 - 11 3.370870 2 + 12 3.508560 6 + 13 3.616820 2 + 14 3.633000 2 + 15 3.699490 1 - 16 3.711000 3 - 17 3.738570 1 + 18 3.782460 4 - 19 3.802800 2 - 20 3.852000 0 + 21 3.852260 3 - 22 4.035160 2 + 23 4.045990 5 - 24 4.074530 2 + 25 4.077000 4 + 26 4.102000 1 + 27 4.196890 1 - 28 4.205300 1 + 29 4.210000 2 - 30 4.254500 1 + 31 4.311000 1 + 32 4.348000 1 - 33 4.381000 3 + 34 4.387690 2 + 35 4.398000 5 + 36 4.404000 5 - 37 4.407000 2 + 38 4.457450 3 + 39 4.472000 3 - 40 4.530000 3 - ----------------------- * 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 --------------------------------------------------------- Ti-49 7.262 1.714 0.240 1.214 -0.551 8.517 3.990 Ti-48 6.709 3.464 0.659 1.569 -1.852 14.944 4.530 Ti-47 5.775 1.750 0.721 1.959 -6.004 17.447 2.868 Sc-48 5.484 0.000 0.205 1.766 -4.190 11.390 3.026 Sc-47 7.190 1.750 1.556 1.225 -1.430 8.955 2.650 Sc-46 6.314 0.000 1.456 1.397 -3.453 8.080 2.062 Ca-47 7.478 1.750 0.226 1.252 -1.162 9.463 3.267 Ca-46 7.069 3.539 1.494 1.040 2.082 8.748 5.851 Ca-45 7.086 1.789 2.009 1.267 -2.005 9.502 1.973 Ca-44 6.420 3.618 2.154 1.408 -0.683 12.170 4.824 --------------------------------------------------------- * Gamma-ray strength functions for Ti-49 E1: hybrid model(GH)/10/ ER= 19.29 (MeV) EG= 7.41 (MeV) SIG= 74.95 (mb) M1: standard lorentzian model(SLO) ER= 11.20 (MeV) EG= 4.00 (MeV) SIG= 2.08 (mb) E2: standard lorentzian model(SLO) ER= 17.22 (MeV) EG= 5.52 (MeV) SIG= 1.06 (mb) References #b8) D.A.Brown et al., Nucl. 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