51-Sb-125 JAEA EVAL-MAR13 K.Shibata JNST 51, 425 (2014) DIST-DEC21 20180518 ----JENDL-5 MATERIAL 5137 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 13-03 Re-evaluation was performed by K. Shibata (JAEA)./1/ 13-06 Thermal capture cross section was revised. 18-05 Activation cross sections added by K.Shibata. 21-11 revised by O.Iwamoto (MF8/MT4) added 21-11 above 20 MeV, JENDL/ImPACT-2018 merged by O.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 No resolved resonance parameters Unresolved resonance region: 40 eV - 400 keV The parameters were obtained by fitting to the evaluated total and capture cross sections. The unresolved resonance parameters obtained should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 6.0322E+00 Elastic 4.6958E+00 n,gamma 1.3339E+00 3.2119E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /2/. MT= 2 Elastic scattering cross section The cross section was obtained by subtracting the non-elastic cross section from the total cross section. Below 40 eV, the cross section was set to 4.67641 barns. 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 /2/. MT= 16 (n,2n) cross section Calculated with POD code /2/. MT= 17 (n,3n) cross section Calculated with POD code /2/. MT= 22 (n,na) cross section Calculated with POD code /2/. MT= 28 (n,np) cross section Calculated with POD code /2/. MT= 32 (n,nd) cross section Calculated with POD code /2/. MT=102 Capture cross section Calculated with POD code /2/. Below 40 eV, an 1/v shape was assumed with 1.3333 barns /1/ at 0.0253 eV. MT=103 (n,p) cross section Calculated with POD code /2/. MT=104 (n,d) cross section Calculated with POD code /2/. MT=105 (n,t) cross section Calculated with POD code /2/. MT=106 (n,He3) cross section Calculated with POD code /2/. MT=107 (n,a) cross section Calculated with POD code /2/. MT=203 (n,xp) cross section Calculated with POD code /2/. MT=204 (n,xd) cross section Calculated with POD code /2/. MT=205 (n,xt) cross section Calculated with POD code /2/. MT=206 (n,xHe3) cross section Calculated with POD code /2/. MT=207 (n,xa) cross section Calculated with POD code /2/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/2/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/2/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/2/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/2/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/2/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/2/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/2/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/2/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/2/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/2/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/2/. 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= 9 Isomeric branching ratios MT=102 (n,g) reaction Calculated with POD code /2/. MF=10 Nuclide production cross sections MT= 16 Partial (n,2n) reactions Calculated with POD code /2/. MT= 22 Partial (n,na) reactions Calculated with POD code /2/. MT= 32 Partial (n,nd) reactions Calculated with POD code /2/. MT=103 Partial (n,p) reactions Calculated with POD code /2/. MT=105 Partial (n,t) reactions Calculated with POD code /2/. MT=106 Partial (n,He3) reactions Calculated with POD code /2/. MT=107 Partial (n,a) reactions Calculated with POD code /2/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /2/. 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 /2/. *************************************************************** * Nuclear Model Calculations with POD Code /2/ * *************************************************************** 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 /3/ Protons: Koning and Delaroche /4/ Deuterons: Lohr and Haeberli /5/ Tritons: Becchetti and Greenlees /6/ He-3: Becchetti and Greenlees /6/ Alphas: Lemos /7/ potentials modified by Arthur and Young /8/ 3. Level scheme of Sb-125 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 7/2 + 1 0.33214 5/2 + 2 0.64320 3/2 + 3 0.92170 1/2 + 4* 1.06730 9/2 + 5 1.08963 11/2 + 6 1.34946 7/2 + 7 1.41987 9/2 + 8 1.48410 5/2 + 9 1.56000 5/2 + 10 1.59158 9/2 + 11 1.66000 9/2 + 12 1.70090 3/2 + 13 1.73570 3/2 + 14 1.80000 1/2 + 15 1.80670 9/2 + 16 1.88986 11/2 - 17 1.89400 7/2 + 18 1.91350 9/2 - 19 1.94740 3/2 + 20 1.98288 11/2 - 21 2.00214 9/2 - 22 2.11300 3/2 - 23 2.20102 11/2 + 24 2.22710 9/2 + 25 2.24079 9/2 + 26 2.25347 9/2 - 27 2.27577 9/2 - 28 2.28825 11/2 + 29 2.29900 3/2 - ------------------------- Levels above 2.30900 MeV are assumed to be continuous. The symbol (*) stands for the excited level involved in the coupled-channel calculation. A giant resonance, which was estimated from DWBA, was added to the continuum at Ex = 2.3 MeV. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /9/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Sb-126 15.534 0.000 -0.617 0.741 -2.251 6.198 0.128 Sb-125 14.870 1.073 -0.068 0.553 0.610 4.053 2.299 Sb-124 14.872 0.000 0.763 0.688 -1.937 5.528 0.643 Sb-123 14.667 1.082 1.092 0.594 0.036 5.016 1.773 Sn-125 16.177 1.073 -1.437 0.622 0.148 5.007 0.855 Sn-124 15.404 2.155 -0.998 0.704 0.534 7.380 2.879 Sn-123 15.969 1.082 -0.017 0.714 -1.324 7.311 1.301 In-123 14.667 1.082 0.204 0.520 0.800 3.642 2.186 In-122 15.117 0.000 0.977 0.559 -0.857 3.517 0.229 In-121 14.463 1.091 1.390 0.614 -0.170 5.389 1.504 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /10/ 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. 51, 425 (2014). 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 3) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 4) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 5) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 6) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 7) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 8) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 9) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 10) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).