44-Ru-100 JAEA EVAL-JUL12 K.Shibata JNST 50, 1177 (2013) DIST-DEC21 20180517 ----JENDL-5 MATERIAL 4437 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 12-07 The fast neutron cross sections were re-evaluated by K. Shibata (JAEA) /1/ using the POD code. 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 Resolved resonance region (MLBW; below 11.89 keV) Resonance parameters were taken from JENDL-2 except for those of negative and hypothetical resonances, angular momentum for some levels and scattering radius. For JENDL-2, the 228.5-eV resonance was adopted from Priesmeyer and Jung/2/. Resonances above 2679.7 eV were mainly based on the experimental data of Macklin and Halperin /3/. Resonances at 120 eV and between 336 and 2497 eV are hypothetical levels generated by assuming S0=0.43e-4, D0=340 eV, S1=4.1e-4, D1=110 eV. The average radiation width of 0.124+-0.017 eV was deduced and adopted for the levels whose radiation width was unknown. Two negative resonances were added, and parameters of the 120-eV level were adjusted so as to reproduce the capture cross section of 5.0+-0.6 barns at 0.0253 eV and the capture resonance integral of 11.2+-1.1 barns/4/. For JENDL-3, the reduced neutron width was decreased from 43 meV to 23 meV. Scattering radius was changed to 6.1 fm according to the systematics of measured values. Number of negative resonances was reduced to one and its parameters were reevaluated. Neutron orbital angular momentum l of some resonances was estimated with a method of Bollinger and Thomas /5/. For JENDL-4.0, the capture width of a negative resonance was adjusted so as to repruduce the measured thermal cross section of 5.8 +- 0.4/6/ Unresolved resonance region: 11.89 keV - 300 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 /7/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 1.2341E+01 Elastic 6.4984E+00 n,gamma 5.8421E+00 1.1425E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /7/. MT= 2 Elastic scattering cross section The cross section was obtained by subtracting the non-elastic cross section from the total cross section. 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 /7/. MT= 16 (n,2n) cross section Calculated with POD code /7/. MT= 17 (n,3n) cross section Calculated with POD code /7/. MT= 22 (n,na) cross section Calculated with POD code /7/. MT= 28 (n,np) cross section Calculated with POD code /7/. MT= 32 (n,nd) cross section Calculated with POD code /7/. MT=102 Capture cross section Calculated with POD code /7/. MT=103 (n,p) cross section Calculated with POD code /7/. MT=104 (n,d) cross section Calculated with POD code /7/. MT=105 (n,t) cross section Calculated with POD code /7/. MT=106 (n,He3) cross section Calculated with POD code /7/. MT=107 (n,a) cross section Calculated with POD code /7/. MT=203 (n,xp) cross section Calculated with POD code /7/. MT=204 (n,xd) cross section Calculated with POD code /7/. MT=205 (n,xt) cross section Calculated with POD code /7/. MT=206 (n,xHe3) cross section Calculated with POD code /7/. MT=207 (n,xa) cross section Calculated with POD code /7/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /7/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/7/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/7/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/7/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/7/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/7/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 85 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 86 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 87 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 88 (n,n') reaction Neutron angular distributions calculated with POD/7/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/7/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/7/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/7/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/7/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/7/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/7/. 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 /7/. MT=104 Partial (n,d) reactions Calculated with POD code /7/. MT=106 Partial (n,He3) reactions Calculated with POD code /7/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /7/. 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 /7/. *************************************************************** * Nuclear Model Calculations with POD Code /7/ * *************************************************************** 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 /8/ Protons: Koning and Delaroche /9/ Deuterons: Lohr and Haeberli /10/ Tritons: Becchetti and Greenlees /11/ He-3: Becchetti and Greenlees /11/ Alphas: Lemos /12/ potentials modified by Arthur and Young /13/ 3. Level scheme of Ru-100 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.53951 2 + 2 1.13030 0 + 3* 1.22647 4 + 4* 1.36216 2 + 5 1.74099 0 + 6 1.86510 2 + 7 1.88104 3 + 8 2.05165 0 + 9 2.06252 3 - 10 2.07510 4 + 11 2.07610 6 + 12 2.09910 2 + 13 2.13100 2 + 14* 2.16687 3 - 15 2.19400 3 + 16 2.24080 1 + 17 2.26800 3 + 18 2.31350 2 + 19 2.32460 3 + 20 2.35140 2 + 21 2.36650 4 + 22 2.38717 0 + 23 2.41180 3 - 24 2.43800 3 + 25 2.46938 2 - 26 2.49289 2 + 27 2.51245 3 + 28 2.51682 2 - 29 2.52820 5 - 30 2.53617 2 + 31 2.54370 1 + 32 2.56991 3 - 33 2.59185 2 + 34 2.61709 1 + 35 2.63400 4 + 36 2.66013 2 + 37 2.66066 2 + 38 2.66645 1 + ------------------------- Levels above 2.67645 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 /14/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ru-101 13.639 1.194 2.251 0.781 -2.049 8.618 0.742 Ru-100 13.282 2.400 1.290 0.806 -0.534 9.579 2.666 Ru- 99 13.423 1.206 0.677 0.770 -1.114 7.458 1.414 Ru- 98 12.623 2.424 -0.282 0.908 -0.590 10.214 2.720 Tc-100 13.559 0.000 3.025 0.624 -1.658 4.719 0.758 Tc- 99 12.195 1.206 2.485 0.872 -2.450 9.579 1.329 Tc- 98 12.578 0.000 1.601 0.786 -2.453 6.486 0.568 Mo- 98 13.582 2.424 2.452 0.685 0.275 8.035 2.350 Mo- 97 12.902 1.218 1.698 0.757 -1.128 7.419 1.120 Mo- 96 13.196 2.449 1.024 0.752 0.274 8.412 3.007 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /15/ 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., 50, 1177 (2013). 2) H.G.Priesmeyer, H.H.Jung, Atomkernenergie, 19, 111 (1972). 3) R.L.Macklin, J.Halperin, Nucl. Sci. Eng., 73, 174 (1980). 4) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 5) L.M.Bollinger, G.E.Thomas: Phys. Rev., 171,1293 (1968). 6) J.Halperin et al., ORNL 3832, p.4 (1965). 7) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 8) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 9) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 10) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 11) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 12) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 13) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 14) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 15) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).