38-Sr- 86 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-MAY10 20091126 ----JENDL-4.0 MATERIAL 3831 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 09-10 Compiled 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 (MLBW formula) : below 37.12 keV The resolved resonance parameters for JENDL-3 were taken from JENDL-2 which was evaluated on the basis of the measured data by Camarda et al./1/ and Musgrove et al./2/ Those of the first resonance level at 588.4 eV were adjusted so as to reproduce the capture cross section of 1.04+-0.07 barns at 0.0253 eV and its resonance integral of 4.79+-0.24 barns given by Mughabghab et al./3/ Scattering radius was also modified to 7.25 fm on the basis of the graph (Fig.1, part A) of Ref./3/ In JENDL-4.0, the resolved resonance parameters remain unchanged. Unresolved resonance region: 37.12 keV - 1 MeV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /4/. The unresolved parameters 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 5.1981E+00 Elastic 4.1578E+00 n,gamma 1.0403E+00 4.8035E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /4/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from 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 /4/. MT= 16 (n,2n) cross section Calculated with POD code /4/. MT= 22 (n,na) cross section Calculated with POD code /4/. MT= 28 (n,np) cross section Calculated with POD code /4/. MT=102 Capture cross section Calculated with POD code /4/. MT=103 (n,p) cross section Calculated with POD code /4/. MT=104 (n,d) cross section Calculated with POD code /4/. MT=105 (n,t) cross section Calculated with POD code /4/. MT=106 (n,He3) cross section Calculated with POD code /4/. MT=107 (n,a) cross section Calculated with POD code /4/. MT=203 (n,xp) cross section Calculated with POD code /4/. MT=204 (n,xd) cross section Calculated with POD code /4/. MT=205 (n,xt) cross section Calculated with POD code /4/. MT=206 (n,xHe3) cross section Calculated with POD code /4/. MT=207 (n,xa) cross section Calculated with POD code /4/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /4/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/4/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/4/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/4/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/4/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/4/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/4/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/4/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/4/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/4/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/4/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /4/. 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 /4/.*************************************************************** * Nuclear Model Calculations with POD Code /4/ * *************************************************************** 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 /5/ Protons: Koning and Delaroche /6/ Deuterons: Lohr and Haeberli /7/ Tritons: Becchetti and Greenlees /8/ He-3: Becchetti and Greenlees /8/ Alphas: Lemos /9/ potentials modified by Arthur and Young /10/ 3. Level scheme of Sr- 86 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 1.07668 2 + 2 1.85417 2 + 3 2.10600 0 + 4 2.20300 0 + 5 2.22974 4 + 6 2.36500 4 - 7 2.48191 3 - 8 2.49900 5 + 9 2.64219 2 + 10 2.67284 5 - 11 2.78850 2 + 12 2.85700 6 + 13 2.87828 4 + 14 2.95568 8 + 15 2.99736 3 - 16 3.04500 4 + 17 3.05578 5 - ------------------------- Levels above 3.06578 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /11/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Sr- 87 12.367 1.287 -0.021 0.633 0.786 4.453 2.596 Sr- 86 11.310 2.588 0.767 0.818 0.770 8.345 3.056 Sr- 85 11.114 1.302 1.863 0.862 -1.338 8.278 1.794 Sr- 84 11.089 2.619 1.992 0.730 1.218 7.405 3.279 Rb- 86 9.932 0.000 0.007 0.898 -1.348 5.547 1.738 Rb- 85 10.720 1.302 1.529 0.855 -0.855 7.650 2.088 Rb- 84 11.060 0.000 2.125 0.783 -1.914 5.688 0.797 Kr- 84 11.089 2.619 1.235 0.745 1.364 7.286 3.951 Kr- 83 11.668 1.317 2.381 0.710 -0.316 6.290 1.889 Kr- 82 10.867 2.650 2.503 0.781 0.700 8.353 3.187 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /12/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) H.Camarda et al., NCSAC-31, 40 (1970). 2) A.R.de L.Musgrove et al., Proc. Int. Conf. on Neutron Physics and Nucl. Data for Reactors, Harwell 1978, 449. 3) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 4) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 5) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 6) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 7) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 8) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 9) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 10) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 11) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 12) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).