68-Er-162 JAEA EVAL-OCT11 K.Shibata (JAEA) JNST 49, 824 (2012) DIST-DEC21 20180515 ----JENDL-5 MATERIAL 6825 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2011-10 Re-evaluated/1/ by K.Shibata. 2018-05 Activation cross sections added by K.Shibata. 21-11 revised by O.Iwamoto (MF8/MT4) added MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters Resolved resonance parameters (MLBW formula): below 250 eV Resolved resonance parameters were taken from ref./2/ The bound level at -32.5 eV has Gamma-n = 0.11967 eV and Gamma-gamma = 0.1 eV. This choice gives the desired value for the thermal capture cross section, 19+-2 b /3/. Values of Gamma-gamma not given in Ref./2/ are set to 0.1 eV. The value for the scattering radius is 8.1fm. Highest energy resonance included is 250.0 eV. No background cross section is given. RRP's remain unchanged from JENDL-4.0. Unresolved resonance region: 250 eV - 100 keV The parameters were obtained by fitting to the calculated total and capture cross sections. The unresolved resonance parameters obtained should be used only for self-shielding calculation. URP's were re-calculated by fitting to the total and capture cross sections calculated with POD./4/ Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 2.6946E+01 Elastic 8.0278E+00 n,gamma 1.8918E+01 4.7902E+02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /4/. MT= 2 Elastic scattering cross section The elastic scattering cross section was obtained by subtracting the non-elastic cross section from the total cross sections. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT= 4,51-91 (n,n') cross section Calculated with POD code /4/. MT= 16 (n,2n) cross section Calculated with POD code /4/. MT= 17 (n,3n) cross section Calculated with POD code /4/. MT= 22 (n,na) cross section Calculated with POD code /4/. MT= 28 (n,np) cross section Calculated with POD code /4/. MT= 32 (n,nd) cross section Calculated with POD code /4/. MT=102 Capture cross section Calculated with POD code /4/. MT=103 (n,p) cross section Calculated with POD code /4/. MT=104 (n,d) cross section Calculated with POD code /4/. MT=105 (n,t) cross section Calculated with POD code /4/. MT=106 (n,He3) cross section Calculated with POD code /4/. MT=107 (n,a) cross section Calculated with POD code /4/. MT=203 (n,xp) cross section Calculated with POD code /4/. MT=204 (n,xd) cross section Calculated with POD code /4/. MT=205 (n,xt) cross section Calculated with POD code /4/. MT=206 (n,xHe3) cross section Calculated with POD code /4/. MT=207 (n,xa) cross section Calculated with POD code /4/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /4/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/4/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/4/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/4/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/4/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/4/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/4/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/4/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/4/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/4/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/4/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/4/. MF= 8 Information on decay data MT= 16 (n,2n) reaction MT= 17 (n,3n) reaction MT= 22 (n,na) reaction MT= 28 (n,np) reaction MT= 32 (n,nd) reaction MT=102 (n,g) reaction MT=103 (n,p) reaction MT=104 (n,d) reaction MT=105 (n,t) reaction MT=106 (n,He3) reaction MT=107 (n,a) reaction MF=10 Nuclide production cross sections MT= 28 Partial (n,np) reactions Calculated with POD code /4/. MT= 32 Partial (n,nd) reactions Calculated with POD code /4/. MT=103 Partial (n,p) reactions Calculated with POD code /4/. MT=104 Partial (n,d) reactions Calculated with POD code /4/. MT=105 Partial (n,t) reactions Calculated with POD code /4/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /4/. MF=14 Gamma-ray angular distributions MT= 3 Non-elastic gamma emission Assumed to be isotropic. MF=15 Gamma-ray spectra MT= 3 Non-elastic gamma emission Calculated with POD code /4/. *************************************************************** * Nuclear Model Calculations with POD Code /4/ * *************************************************************** 1. Theoretical models The POD code is based on the spherical optical model, the distorted-wave Born approximaiton (DWBA), one-component exciton preequilibrium model, and the Hauser-Feshbach-Moldauer statis- tical model. With the preequilibrim model, semi-empirical pickup and knockout process can be taken into account for composite-particle emission. The gamma-ray emission from the compound nucleus can be calculated within the framework of the exciton model. The code is capable of reading in particle transmission coefficients calculated by separate spherical or coupled-channel optical model code. 2. Optical model parameters Neutrons: Coupled-channel optical model parameters /5/ Note that V_R0 was changed to -38.0 MeV from the original value. Protons: Koning and Delaroche /6/ Deuterons: Lohr and Haeberli /7/ Tritons: Becchetti and Greenlees /8/ He-3: Becchetti and Greenlees /8/ Alphas: Lemos /9/ potentials modified by Arthur and Young /10/ 3. Level scheme of Er-162 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.10204 2 + 2* 0.32962 4 + 3* 0.66668 6 + 4* 0.90072 2 + 5* 1.00206 3 + 6 1.08716 0 + 7* 1.09670 8 + 8* 1.12811 4 + 9 1.17102 2 + 10 1.28622 5 + 11 1.35217 1 - 12* 1.35677 3 - 13 1.36900 4 + 14 1.41258 2 + 15 1.42045 2 - 16 1.42979 2 + 17 1.45958 6 + 18 1.46912 5 - 19 1.50058 2 + 20 1.50636 1 - 21 1.54262 4 - 22 1.57284 2 - 23 1.59400 1 - 24 1.60283 10 + 25 1.62324 3 - ------------------------- Levels above 1.63324 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /11/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Er-163 20.272 0.940 3.040 0.510 -1.130 5.846 0.735 Er-162 19.349 1.886 3.006 0.527 -0.161 6.852 1.623 Er-161 19.842 0.946 3.339 0.531 -1.389 6.270 0.621 Er-160 19.144 1.897 3.217 0.527 -0.155 6.863 1.008 Ho-162 19.219 0.000 2.893 0.370 -0.399 2.119 0.766 Ho-161 18.473 0.946 3.157 0.527 -0.906 5.679 0.827 Ho-160 19.017 0.000 3.460 0.454 -1.210 3.565 0.170 Dy-160 19.144 1.897 2.875 0.579 -0.774 7.872 1.708 Dy-159 19.642 0.952 3.162 0.543 -1.455 6.419 0.576 Dy-158 18.939 1.909 3.250 0.583 -0.894 8.056 1.559 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /12/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) K.Shibata, J. Nucl. Sci. Technol., 49, 824 (2012). 2) Landolt-Boernstein New Series I/16B (Aug 1998). 3) S. F. Mughabghab, "Neutron Cross Sections: Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections, Part B: Z=61-100," Academic Press (1984). 4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 6) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 7) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 8) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 9) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 10) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 11) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 12) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).