22-Ti- 44 JAEA EVAL-Aug21 N.Iwamoto DIST-DEC21 20210820 ----JENDL-5 MATERIAL 2219 -----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 3.28051E+00 Elastic 1.74050E+00 n,gamma 1.10029E+00 6.73551E-01 n,p 3.62926E-01 2.30254E-01 n,alpha 7.40235E-03 4.80962E-03 ---------------------------------------------------------- (*) 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= 44 (n,n2p) cross section Calculated with CCONE code /1/. MT= 45 (n,npa) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. The thermal cross section was derived from Mughabghab/2/. Below 3.43keV the cross section of 1/v shape was adopted. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. Below 3.43keV 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 3.43keV 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= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 44 (n,n2p) reaction Calculated with CCONE code /1/. MT= 45 (n,npa) 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= 28 (n,np) 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= 45 (n,npa) 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= 32 (n,nd) reaction Calculated with CCONE code /1/. MT=105 (n,t) 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-44 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 1.083060 2 + 2 1.904300 0 + 3 2.454330 4 + 4 2.530980 2 + 5 2.886600 2 + 6 3.175800 3 - 7 3.364000 4 + 8 3.415300 2 + 9 3.645800 4 - 10 3.755900 1 - 11 3.942700 3 - 12 3.980000 4 + 13 4.015310 6 + 14 4.061000 3 - 15 4.115600 2 + 16 4.227000 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-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 Ti-43 6.701 1.830 1.278 1.359 -1.861 10.044 1.858 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 Sc-42 6.578 0.000 -0.456 1.331 -2.028 7.190 3.146 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-45 E1: hybrid model(GH)/9/ ER= 19.69 (MeV) EG= 7.71 (MeV) SIG= 66.85 (mb) M1: standard lorentzian model(SLO) ER= 11.53 (MeV) EG= 4.00 (MeV) SIG= 2.27 (mb) E2: standard lorentzian model(SLO) ER= 17.71 (MeV) EG= 5.57 (MeV) SIG= 1.15 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.F.Mughabghab, Atlas of Neutron Resonances, 6th Ed. (2018) ) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) ) Y.Han et al., Phys. Rev. C 74,044615(2006) 5) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 (2011) ) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) ) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) ) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) ) S. Goriely, Phys. Lett. B436, 10 (1998)