68-Er-170 JAEA EVAL-NOV11 K. Shibata (JAEA) JNST 49, 824 (2012) DIST-DEC21 20180516 ----JENDL-5 MATERIAL 6849 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2011-11 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 region: below 3 keV Resolved resonance parameters were taken from /2/. The bound level at -336.0 eV has Gamma-n = 13.0645 eV and Gamma-gamma = 0.082 eV. This choice gives the desired value for the thermal capture cross section, 5.8+-0.3 b. Values of gamma-gamma not given in Ref./2/ are set to 0.092 eV. 21 resonances [L=1] did not have values given for "J", 10 are assigned to J= 0.5 and the remaining 11 to J= 1.5 by random method. The value for the scattering radius is 8.0 fm, taken from Ref./3/ 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 /3/. Highest energy resonance included is 2977.8 eV. No background cross sections are given. In JENDL-4.0, the negative resonance was adjusted so as to reproduce the thermal cross sections recommended by Mughabghab /4/. RRP's remain unchanged from JENDL-4.0 Unresolved resonance region: 3 - 650 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 2.1685E+01 Elastic 1.2828E+01 n,gamma 8.8572E+00 4.6429E+01 ---------------------------------------------------------- (*) 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 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 Calculated with POD code /5/. 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= 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= 32 Partial (n,nd) reactions Calculated with POD code /5/. MT=103 Partial (n,p) reactions Calculated with POD code /5/. MT=105 Partial (n,t) 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 /6/ Protons: Koning and Delaroche /7/ Deuterons: Lohr and Haeberli /8/ Tritons: Becchetti and Greenlees /9/ He-3: Becchetti and Greenlees /9/ Alphas: Lemos /10/ potentials modified by Arthur and Young /11/ 3. Level scheme of Er-170 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.07860 2 + 2* 0.26015 4 + 3* 0.54072 6 + 4 0.89089 0 + 5* 0.91502 8 + 6* 0.93403 2 + 7 0.96000 2 + 8* 1.01054 3 + 9 1.10336 4 + 10* 1.12732 4 + 11 1.21750 3 + 12 1.23661 5 + 13 1.26664 1 - 14 1.26869 4 - 15 1.30400 3 - 16 1.30458 4 + 17 1.30525 2 - 18 1.32429 0 + 19 1.33200 2 + 20 1.33500 4 + 21* 1.34021 3 - 22 1.35050 6 + 23 1.37060 3 - 24 1.37210 5 - 25 1.37660 10 + 26 1.38541 2 + 27 1.40196 6 + 28 1.41314 5 + 29 1.41625 2 + 30 1.42210 5 - 31 1.43297 4 - 32 1.48336 3 + 33 1.48381 5 - 34 1.48791 5 + 35 1.49609 6 - 36 1.50087 4 + 37 1.50623 2 - 38 1.52642 4 + 39 1.53900 1 - 40 1.54348 6 + ------------------------- Levels above 1.55348 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 /12/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Er-171 20.616 0.918 1.520 0.517 -0.876 5.556 0.615 Er-170 20.165 1.841 1.740 0.579 -0.754 7.764 1.543 Er-169 19.931 0.923 1.659 0.517 -0.753 5.419 0.770 Er-168 19.559 1.852 1.843 0.560 -0.322 7.166 1.768 Ho-170 20.024 0.000 1.480 0.386 -0.390 2.209 0.140 Ho-169 19.261 0.923 1.801 0.553 -1.064 5.984 0.359 Ho-168 19.823 0.000 1.550 0.488 -1.290 3.868 0.193 Dy-168 19.962 1.852 1.924 0.494 0.366 5.992 0.873 Dy-167 20.440 0.929 1.843 0.585 -1.889 7.134 0.098 Dy-166 19.758 1.863 2.008 0.556 -0.373 7.221 1.351 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /13/ 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) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 7) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 8) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 9) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 10) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 11) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 12) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 13) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).