68-Er-167 JAEA EVAL-NOV11 K. Shibata (JAEA) JNST 49, 824 (2012) DIST-DEC21 20180515 ----JENDL-5 MATERIAL 6840 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2011-11 Re-evaluated /1/ by K.Shibata. 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 591 eV The multilevel Breit-Wigner formula was used. Resolved resonance parameters from Ref./2/ or /3/. Values of Gamma-gamma not given in Ref./2/ or /3/ are set to 0.089 eV. 30 resonances did not have values given for "J", 21 are assigned to J= 3 and the remaining 9 to J= 4 by random method. The value for the scattering radius is 8.2fm, taken from Ref./4/ with small change with in the given error, so as to produce the close value of the thermal neutron scattering cross section recommended by Mughabghab (Ref. /4/). Highest energy resonance included is 590.1 eV. No background cross sections were given. In JENDL-4.0, the parameters for 7.92- and 9.39-eV resonances were replaced with those for 7.93- and 9.389-eV resonances measured by Danon et al./3/ RRP's remain unchanged from JENDL-4.0 Unresolved resonance region: 591 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 by POD /5/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 6.4555E+02 Elastic 1.3345E+00 n,gamma 6.4421E+02 2.9999E+03 n,alpha 7.0030E-05 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /5/. 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 /5/. MT= 16 (n,2n) cross section Calculated with POD code /5/. MT= 17 (n,3n) cross section Calculated with POD code /5/. MT= 22 (n,na) cross section Calculated with POD code /5/. MT= 28 (n,np) cross section Calculated with POD code /5/. MT= 32 (n,nd) cross section Calculated with POD code /5/. MT=102 Capture cross section Calculated with POD code /5/. MT=103 (n,p) cross section Calculated with POD code /5/. MT=104 (n,d) cross section Calculated with POD code /5/. MT=105 (n,t) cross section Calculated with POD code /5/. MT=106 (n,He3) cross section Calculated with POD code /5/. MT=107 (n,a) cross section Below 591 eV, a 1/v curve was assumed with 0.07 mb at 0.0253 eV, which was recommended by Mughabghab /6/. Above 591 eV, the cross section was calculated with POD code /5/. MT=203 (n,xp) cross section Calculated with POD code /5/. MT=204 (n,xd) cross section Calculated with POD code /5/. MT=205 (n,xt) cross section Calculated with POD code /5/. MT=206 (n,xHe3) cross section Calculated with POD code /5/. MT=207 (n,xa) cross section Sum of (n,na) and (n,a) cross sections mentioned above. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/5/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/5/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/5/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/5/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/5/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 85 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 86 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 87 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 88 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 89 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 90 (n,n') reaction Neutron angular distributions calculated with POD/5/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/5/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/5/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/5/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/5/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/5/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/5/. MF= 8 Information on decay data MT= 4 (n,n') reaction 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= 4 Partial (n,n') reactions Calculated with POD code /5/. MT= 28 Partial (n,np) reactions Calculated with POD code /5/. MT=104 Partial (n,d) reactions Calculated with POD code /5/. MT=106 Partial (n,He3) reactions Calculated with POD code /5/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /5/. 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 /5/. *************************************************************** * Nuclear Model Calculations with POD Code /5/ * *************************************************************** 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 /7/ Note that V_R0 was changed to -38.0 MeV from the original value. Protons: Koning and Delaroche /8/ Deuterons: Lohr and Haeberli /9/ Tritons: Becchetti and Greenlees /10/ He-3: Becchetti and Greenlees /10/ Alphas: Lemos /11/ potentials modified by Arthur and Young /12/ 3. Level scheme of Er-167 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 7/2 + 1* 0.07932 9/2 + 2* 0.17797 11/2 + 3+ 0.20780 1/2 - 4+ 0.26487 3/2 - 5+ 0.28157 5/2 - 6* 0.29495 13/2 + 7 0.34655 5/2 - 8+ 0.41327 7/2 - 9 0.43003 7/2 - 10 0.43445 15/2 + 11+ 0.44198 9/2 - 12 0.53154 3/2 + 13 0.53580 9/2 - 14 0.57376 5/2 + 15 0.58737 17/2 + 16 0.59179 9/2 + 17 0.59800 9/2 - 18 0.64025 7/2 + 19+ 0.64521 11/2 - 20 0.66248 11/2 - 21 0.66790 5/2 - 22+ 0.68331 13/2 - 23 0.71106 11/2 + 24 0.71111 9/2 + 25 0.73000 3/2 - 26 0.74532 7/2 - 27 0.75272 3/2 - 28 0.76346 1/2 - 29 0.77269 19/2 + 30 0.79097 11/2 + 31 0.80164 3/2 - 32 0.81010 11/2 - 33 0.81052 5/2 + 34 0.81200 13/2 - 35 0.81248 5/2 - 36 0.82832 13/2 + 37 0.84527 9/2 - 38 0.85647 5/2 - 39 0.87306 7/2 + 40 0.87840 13/2 + ------------------------- Levels above 0.88840 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. The symbol (+) stands for the excited level involved in the DWBA calculation. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /13/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Er-168 19.559 1.852 1.843 0.560 -0.322 7.166 1.768 Er-167 19.951 0.929 1.916 0.564 -1.449 6.503 0.878 Er-166 19.758 1.863 2.177 0.540 -0.216 6.951 1.948 Er-165 19.721 0.934 2.568 0.545 -1.312 6.241 0.590 Ho-167 19.065 0.929 1.863 0.546 -0.942 5.808 0.570 Ho-166 18.616 0.000 1.715 0.555 -1.814 4.856 0.597 Ho-165 18.868 0.934 2.069 0.556 -1.068 6.014 1.056 Dy-165 19.645 0.934 1.905 0.561 -1.310 6.327 0.706 Dy-164 19.078 1.874 2.014 0.569 -0.344 7.275 1.303 Dy-163 19.156 0.940 2.163 0.569 -1.365 6.445 0.660 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /14/ 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) Y.Danon et al., Nucl. Sci. Eng., 128, 61 (1998). 4) S.F.Mughabghab, "Neutron Cross Sections: Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections, Part B: Z=61-100," Academic press (1984). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 7) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 8) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 9) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 10) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 11) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 12) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 13) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 14) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).