22-Ti- 45 JAEA EVAL-Aug21 N.Iwamoto DIST-DEC21 20210820 ----JENDL-5 MATERIAL 2222 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-08 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 3.7 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 2.53033E+01 Elastic 1.74006E+00 n,gamma 1.01412E+00 5.75163E+00 n,p 2.21485E+01 1.30744E+02 n,alpha 2.41322E-01 1.42511E+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= 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= 41 (n,2np) cross section Calculated with CCONE code /1/. MT= 44 (n,n2p) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Shibata/2/. Below 206eV the cross section of 1/v shape was adopted. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. Below 206eV the cross section of 1/v shape was adopted. 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/. Below 206eV the cross section of 1/v shape was adopted. MT=108 (n,2a) cross section Calculated with CCONE code /1/. MT=111 (n,2p) cross section Calculated with CCONE code /1/. MT=112 (n,pa) cross section Calculated with CCONE code /1/. MT=115 (n,pd) cross section Calculated with CCONE code /1/. MT=116 (n,pt) cross section Calculated with CCONE code /1/. MT=117 (n,da) 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= 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= 41 (n,2np) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) 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=108 (n,2a) reaction Calculated with CCONE code /1/. MT=111 (n,2p) reaction Calculated with CCONE code /1/. MT=112 (n,pa) reaction Calculated with CCONE code /1/. MT=115 (n,pd) reaction Calculated with CCONE code /1/. MT=116 (n,pt) reaction Calculated with CCONE code /1/. MT=117 (n,da) 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= 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= 41 (n,2np) reaction Decay chain is given in the decay data file. MT= 44 (n,n2p) 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=108 (n,2a) 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. MT=115 (n,pd) reaction Decay chain is given in the decay data file. MT=116 (n,pt) reaction Decay chain is given in the decay data file. MT=117 (n,da) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=103 (n,p) reaction Calculated with CCONE code /1/. MF=10 Nuclide production cross sections MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT=104 (n,d) reaction Calculated with CCONE code /1/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : local OMP, A.J.Koning and J.P.Delaroche/3/ modified proton : global OMP, A.J.Koning and J.P.Delaroche/3/ deuteron: Y.Han et al./4/ triton : folding OMP, A.J.Koning and J.P.Delaroche/3/ He-3 : Y.Xu et al. /5/ alpha : L.McFadden and G.R.Satchler/6/ * Level scheme of Ti-45 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 7/2 - 1 0.036530 3/2 - 2 0.039390 5/2 - 3 0.329300 3/2 + 4 0.743880 5/2 + 5 1.226500 7/2 + 6 1.353490 9/2 - 7 1.468240 11/2 - 8 1.521700 9/2 - 9 1.565400 1/2 + 10 1.799000 7/2 + 11 1.881760 9/2 + 12 1.958200 3/2 + 13 2.014700 3/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/7/) Energy dependent parameters of Mengoni-Nakajima/8/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Ti-46 7.069 3.539 0.544 1.587 -2.726 16.222 4.039 Ti-45 6.947 1.789 0.690 1.330 -1.517 9.905 2.015 Ti-44 6.824 3.618 -0.326 1.463 -0.044 13.493 4.227 Sc-45 6.947 1.789 2.027 1.355 -2.731 10.518 2.590 Sc-44 6.824 0.000 1.161 1.293 -3.133 7.468 1.957 Sc-43 6.701 1.830 1.217 1.397 -2.186 10.569 3.123 Ca-44 6.420 3.618 2.154 1.408 -0.683 12.170 4.824 Ca-43 6.325 1.830 1.993 1.432 -2.462 10.494 3.097 Ca-42 6.578 3.703 1.242 1.407 -0.261 12.361 5.017 Ca-41 6.321 1.874 -0.148 1.429 -0.842 10.107 4.648 Ca-40 6.329 3.795 -2.063 1.494 2.096 12.924 7.658 --------------------------------------------------------- * Gamma-ray strength functions for Ti-46 E1: hybrid model(GH)/9/ ER= 19.59 (MeV) EG= 7.63 (MeV) SIG= 68.93 (mb) M1: standard lorentzian model(SLO) ER= 11.44 (MeV) EG= 4.00 (MeV) SIG= 2.22 (mb) E2: standard lorentzian model(SLO) ER= 17.58 (MeV) EG= 5.56 (MeV) SIG= 1.13 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) K.Shibata, J. Nucl. Sci. Technol., 51, 425 (2014) 3) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 4) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) 6) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 7) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 8) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 9) S. Goriely, Phys. Lett. B436, 10 (1998)