71-Lu-170 JAEA EVAL-Sep21 N.Iwamoto DIST-DEC21 20210910 ----JENDL-5 MATERIAL 7110 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2021-09 Evaluated with CCONE code by niwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Scattering radius only AP is assumed to be 7.83 fm. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 9.59745E+01 Elastic 7.72767E+00 n,gamma 8.78725E+01 1.74916E+03 n,p 1.42700E-02 2.84082E-01 n,alpha 6.00907E-03 1.19618E-01 ---------------------------------------------------------- (*) 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= 17 (n,3n) 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= 33 (n,nt) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) 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/. 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= 17 (n,3n) 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= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) 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=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= 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= 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= 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= 22 (n,na) reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MF=10 Nuclide production cross sections MT= 4 (n,n') reaction Calculated with CCONE code /1/. MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. 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 : S.Kunieda et al./2/ proton : 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 Lu-170 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.044510 2 + 2 0.092910 4 - 3 0.096030 3 - 4 0.098530 1 + 5 0.114900 3 + 6 0.116010 1 + 7 0.152070 4 + 8 0.164730 1 - 9 0.170020 2 + 10 0.176620 3 + 11 0.198390 1 + 12 0.206820 5 + 13 0.212510 1 - 14 0.237670 4 + 15 0.244840 1 - 16 0.262670 4 + 17 0.283880 2 - 18 0.304160 1 - 19 0.311850 5 + 20 0.315640 3 + 21 0.316010 5 + 22 0.328890 6 + 23 0.349000 1 + 24 0.375730 7 + 25 0.391450 4 + 26 0.407490 0 - 27 0.411620 6 + 28 0.428080 6 + 29 0.436900 0 + ----------------------- * 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 --------------------------------------------------------- Lu-171 20.480 0.918 2.429 0.539 -1.417 5.751 0.395 Lu-170 20.381 0.000 2.486 0.462 -1.347 3.402 0.437 Lu-169 20.281 0.923 2.740 0.544 -1.535 5.875 0.330 Lu-168 20.182 0.000 2.902 0.462 -1.405 3.438 0.442 Yb-170 19.099 1.841 2.123 0.581 -0.578 6.981 1.718 Yb-169 21.008 0.923 2.324 0.505 -1.051 5.215 0.903 Yb-168 20.182 1.852 2.439 0.533 -0.332 6.485 1.618 Yb-167 20.082 0.929 2.859 0.547 -1.558 5.903 0.477 Yb-166 19.983 1.863 2.790 0.507 -0.025 6.025 1.685 Tm-169 20.281 0.923 2.015 0.528 -1.084 5.381 0.741 Tm-168 20.182 0.000 2.069 0.507 -1.739 4.060 0.393 Tm-167 20.082 0.929 2.439 0.539 -1.310 5.642 0.780 Tm-166 19.983 0.000 2.803 0.461 -1.334 3.352 0.537 Tm-165 19.883 0.934 2.985 0.537 -1.392 5.676 0.552 Tm-164 19.784 0.000 3.324 0.415 -0.927 2.667 0.831 --------------------------------------------------------- * Gamma-ray strength functions for Lu-171 E1: hybrid model(GH)/9/ ER= 12.06 (MeV) EG= 3.02 (MeV) SIG= 150.40 (mb) ER= 15.88 (MeV) EG= 5.11 (MeV) SIG= 300.79 (mb) M1: standard lorentzian model(SLO) ER= 7.39 (MeV) EG= 4.00 (MeV) SIG= 1.00 (mb) E2: standard lorentzian model(SLO) ER= 11.35 (MeV) EG= 4.06 (MeV) SIG= 4.32 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007) 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)