30-Zn- 70 JAEA EVAL-Mar21 N.Iwamoto DIST-DEC21 20210331 ----JENDL-5 MATERIAL 3043 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-12 The resolved resonance parameters were evaluated by N.Iwamoto. The data above the resolved resonance region were evaluated and compiled by N.Iwamoto. 21-03 Evaluated with CCONE code by N.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance region: below 210 keV Resolved resonance parameters were taken from Mughabghab /1/. The negative resonance was placed so as to reproduce the cross sections at thermal energy recommended by Mughabghab /1/. Unresolved resonance region : 210 keV - 800 keV The unresolved resonance paramters (URP) were determined by ASREP code /2/ so as to reproduce the evaluated total and capture cross sections. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barn) (barn) ---------------------------------------------------------- Total 4.42887E+00 Elastic 4.33713E+00 n,gamma 9.17385E-02 9.21179E-02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /3/. MT= 2 Elastic scattering cross section Calculated with CCONE code /3/. MT=4,51-91 (n,n') cross section Calculated with CCONE code /3/. MT= 5 Total reaction (except fission) cross section Calculated with CCONE code /3/. MT= 16 (n,2n) cross section Calculated with CCONE code /3/. MT= 17 (n,3n) cross section Calculated with CCONE code /3/. MT= 22 (n,na) cross section Calculated with CCONE code /3/. MT= 28 (n,np) cross section Calculated with CCONE code /3/. MT= 32 (n,nd) cross section Calculated with CCONE code /3/. MT=102 Capture cross section Calculated with CCONE code /3/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /3/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /3/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /3/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /3/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /3/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 5 Total reaction (except fission) reaction Calculated with CCONE code /3/. MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 17 (n,3n) reaction Calculated with CCONE code /3/. MT= 22 (n,na) reaction Calculated with CCONE code /3/. MT= 28 (n,np) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT=51-91 (n,n') reaction Calculated with CCONE code /3/. MT=102 Capture reaction Calculated with CCONE code /3/. MT=600-649 (n,p) reaction Calculated with CCONE code /3/. MT=650-699 (n,d) reaction Calculated with CCONE code /3/. MT=700-749 (n,t) reaction Calculated with CCONE code /3/. MT=750-799 (n,He3) reaction Calculated with CCONE code /3/. MT=800-849 (n,a) reaction Calculated with CCONE code /3/. 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 /3/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /3/. MT= 32 (n,nd) reaction Calculated with CCONE code /3/. MT=103 (n,p) reaction Calculated with CCONE code /3/. MT=105 (n,t) reaction Calculated with CCONE code /3/. ------------------------------------------------------------------ nuclear model calculation with CCONE code /3/ ------------------------------------------------------------------ * Optical model potentials neutron : S.Kunieda et al./4/ modified proton : A.J.Koning and J.P.Delaroche/5/ deuteron: Y.Han et al./6/ triton : folding OMP, A.J.Koning and J.P.Delaroche/5/ He-3 : Y.Xu et al./7/ alpha : L.McFadden and G.R.Satchler/8/ * Level scheme of Zn-70 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 0 + 1 0.884900 2 + 2 1.070240 0 + 3 1.554000 1 - 4 1.758760 2 + 5 1.786330 4 + 6 1.957220 2 + 7 2.140200 0 + 8 2.375000 2 + 9 2.537880 2 + 10 2.665000 2 + 11 2.692980 4 + 12 2.805000 5 - 13 2.859030 3 - 14 2.894670 6 + 15 2.949230 2 + 16 2.977840 4 + 17 3.037610 5 - 18 3.222720 1 + 19 3.235000 4 + 20 3.246230 4 - 21 3.328000 0 + 22 3.341600 3 - 23 3.419000 3 - 24 3.464000 4 + 25 3.476200 4 - 26 3.506000 5 - 27 3.598410 5 + 28 3.634570 2 + 29 3.680000 0 + 30 3.710300 2 + 31 3.750000 1 - 32 3.755000 8 + 33 3.787650 6 + 34 3.813000 1 - 35 3.844000 1 - 36 3.848000 5 + 37 3.888000 4 + 38 3.903600 5 + 39 3.914000 3 - 40 3.948000 1 - ----------------------- * Level density parameters (Gilbert-Cameron model/9/) Energy dependent parameters of Mengoni-Nakajima/10/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Zn-71 9.909 1.424 3.268 0.829 -0.879 6.489 0.853 Zn-70 9.882 2.869 2.795 0.869 0.768 8.333 3.948 Zn-69 9.542 1.445 2.643 0.893 -0.992 6.936 2.085 Zn-68 8.850 2.910 1.954 1.110 -0.871 10.740 3.726 Cu-70 9.882 0.000 2.643 0.739 -1.277 3.734 0.706 Cu-69 9.769 1.445 2.248 0.536 1.482 3.125 2.800 Cu-68 9.655 0.000 1.710 0.642 -0.308 2.262 1.145 Cu-67 8.777 1.466 1.478 1.009 -0.934 7.572 3.522 Ni-69 9.769 1.445 2.300 0.769 0.104 5.377 0.915 Ni-68 9.655 2.910 1.805 0.755 1.890 6.468 3.558 Ni-67 9.541 1.466 1.435 0.686 1.034 4.057 2.390 Ni-66 9.426 2.954 1.337 0.842 1.570 7.295 4.125 Ni-65 9.064 1.488 1.229 0.885 0.031 6.076 2.906 --------------------------------------------------------- * Gamma-ray strength functions for Zn-71 E1: hybrid model(GH)/11/ ER= 17.65 (MeV) EG= 6.26 (MeV) SIG= 126.88 (mb) M1: standard lorentzian model(SLO) ER= 9.90 (MeV) EG= 4.00 (MeV) SIG= 1.43 (mb) E2: standard lorentzian model(SLO) ER= 15.21 (MeV) EG= 5.26 (MeV) SIG= 1.44 (mb) References 1) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth Edition: Resonance Parameters and Thermal Cross Sections. Z=1-100", Elsevier Science (2006). 2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 3) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 4) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 5) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 6) Y.Han et al., Phys. Rev. C 74,044615(2006) 7) Y.Xu et al., Sci. China, Phys. Mech. & Astron., 54[11], 2005 8) L.McFadden and G.R.Satchler, Nucl. Phys. 84, 177 (1966) 9) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 10) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 11) S. Goriely, Phys. Lett. B436, 10 (1998)