44-Ru-102 JAEA EVAL-JUL12 K.Shibata JNST 50, 1177 (2013) DIST-DEC21 20180517 ----JENDL-5 MATERIAL 4443 -----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. 13-02 The thermal capture cross section was revised by considering the latest measurements. 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 formula) : below 13.4 keV For JENDL-2, resonance energies below 2.5 keV were taken from the data of Priesmeyer and Jung/2/ and Shaw et al. /3/, and for the other resonances above 2.7 keV from Macklin and Halperin/4/. The neutron and radiation widths of large resonances were taken from Priesmeyer and Jung and Macklin and Halperin. For others, the average radiation width of 0.112+-0.027 eV was adopted. For levels observed by Shaw et al. and for three fictitious levels at 2.467, 2.556 and 2.645 keV, the parameters were determined by assuming S0=0.43e-4, D0=340 ev, S1=4.1e-4 and D1=110 eV. Parameters of the negative level added at -146 eV and the first positive level were adjusted to reproduce the capture cross section of 1.21 +-0.07 barns at 0.0253 eV and its resonance integral of 4.2+-0.1 barns/5/. For JENDL-3, neutron and radiation widths of 14 resonances were reevaluated on the basis of the experimental data of Anufriev et al./6/ For the resonances observed by Shaw et al., reduced neutron widths were given as 6.5 meV and 65 meV for s-wave and p-wave resonances, respectively. Parameters of the negative resonance were also revised. Scattering radius was modified from 6.35 fm to 6.1 fm based on the systematics. Neutron orbital angular momentum L of some resonances was estimated with a method of Bollinger and Thomas/7/. For JENDL-4.0, the JENDL-3.3 data were adopted, and parameters of a negative resonance were modified so as to repruduce the thermal total cross setion of 10.4+-0.6 b /6/, capture cross section of 1.48+-0.16 b/8,9,10/. The data of Ishikawa/9/ was multiplied by a factor of 1.26, because standard cross section of Ru-96(n,g) has changed from 0.21 b to 0.27 b. Scattering radius of 6.6 fm was assumed from its systematics/11/. For JENDL-4.0+, the resonance energy of the negative resonance was changed to -146 eV from -160 eV to consider the latest capture measurements /12/ at thermal energy. Unresolved resonance region: 13.4 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 /13/. Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 9.5409E+00 Elastic 8.3627E+00 n,gamma 1.1782E+00 4.2702E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /13/. MT= 2 Elastic scattering cross section The cross section was obatained 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 /13/. MT= 16 (n,2n) cross section Calculated with POD code /13/. MT= 17 (n,3n) cross section Calculated with POD code /13/. MT= 22 (n,na) cross section Calculated with POD code /13/. MT= 28 (n,np) cross section Calculated with POD code /13/. MT= 32 (n,nd) cross section Calculated with POD code /13/. MT=102 Capture cross section Calculated with POD code /13/. MT=103 (n,p) cross section Calculated with POD code /13/. MT=104 (n,d) cross section Calculated with POD code /13/. MT=105 (n,t) cross section Calculated with POD code /13/. MT=106 (n,He3) cross section Calculated with POD code /13/. MT=107 (n,a) cross section Calculated with POD code /13/. MT=203 (n,xp) cross section Calculated with POD code /13/. MT=204 (n,xd) cross section Calculated with POD code /13/. MT=205 (n,xt) cross section Calculated with POD code /13/. MT=206 (n,xHe3) cross section Calculated with POD code /13/. MT=207 (n,xa) cross section Calculated with POD code /13/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /13/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/13/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/13/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/13/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/13/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/13/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/13/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/13/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/13/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/13/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/13/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/13/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/13/. 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= 22 Partial (n,na) reactions Calculated with POD code /13/. MT=103 Partial (n,p) reactions Calculated with POD code /13/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /13/. 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 /13/. *************************************************************** * Nuclear Model Calculations with POD Code /13/ * *************************************************************** 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 /14/ Protons: Koning and Delaroche /15/ Deuterons: Lohr and Haeberli /16/ Tritons: Becchetti and Greenlees /17/ He-3: Becchetti and Greenlees /17/ Alphas: Lemos /18/ potentials modified by Arthur and Young /19/ 3. Level scheme of Ru-102 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1* 0.47508 2 + 2 0.94369 0 + 3 1.10315 2 + 4* 1.10635 4 + 5 1.52166 3 + 6 1.58056 2 + 7 1.60290 3 - 8 1.79871 4 + 9 1.83710 0 + 10 1.87321 6 + 11 1.96865 0 + 12 2.03699 2 + 13* 2.04350 3 - 14 2.15274 4 - 15 2.19000 2 - 16 2.21916 5 + 17 2.24054 2 + 18 2.26123 2 - 19 2.30270 4 + 20 2.36730 3 - 21 2.37060 5 - 22 2.38570 2 - 23 2.42100 4 + 24 2.44180 4 + 25 2.46000 4 + ------------------------- Levels above 2.47000 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 /20/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Ru-103 13.854 1.182 3.548 0.717 -1.842 8.034 0.954 Ru-102 13.056 2.376 2.653 0.711 0.144 8.244 2.460 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 Tc-102 13.006 0.000 4.218 0.592 -1.461 4.334 0.267 Tc-101 12.403 1.194 3.830 0.737 -1.432 7.661 1.271 Tc-100 13.559 0.000 3.025 0.624 -1.658 4.719 0.758 Mo-100 12.840 2.400 3.838 0.682 0.173 8.102 2.339 Mo- 99 13.082 1.206 3.377 0.716 -1.379 7.501 1.405 Mo- 98 13.582 2.424 2.452 0.685 0.275 8.035 2.350 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Modified Lorentzian (MLO) /21/ 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.A.Shaw et al., Bull. Amer. Phys. Soc., 20, 560 (1975). 4) R.L.Macklin, J.Halperin, Nucl. Sci. Eng., 73, 174 (1980). 5) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 6) V.A.Anufriev et al.: Atom. Energiya, 58, 279 (1985). 7) L.M.Bollinger, G.E.Thomas: Phys. Rev., 171, 1293 (1968). 8) P.M.Lantz, ORNL 3832, p.6 (1965). 9) H.Ishikawa, J. Nucl. Sci. Technol., 6, 587 (1969). 10) R.E.Heft, 1978 MAYAG, p.495 (1978). 11) S.F.Mughabghab, "Atlas of Neutron Resonances," Elsevier (2006). 12) K.S.Krane, Phys. Rev., C81, 044310 (2010) 13) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 14) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 15) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 16) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 17) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 18) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 19) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 20) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 21) V.A.Plujko et al., J. Nucl. Sci. Technol. Suppl. 2, 811 (2002).