37-Rb- 85 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-DEC21 20091118 ----JENDL-5 MATERIAL 3725 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-08 Evaluated by K. Shibata, A. Ichihara and S. Kunieda. 09-10 Compiled by K. Shibata. 21-11 revised by O.Iwamoto (MF8/MT16,17,22,28,32,102-107) JENDL/AD-2017 adopted (MF8/MT4) added (MF9/MT102) JENDL/AD-2017 adopted (MF10/MT16,32,103,105,107) JENDL/AD-2017 based 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 8.468 keV Resonance parameters of JENDL-2 were modified as follows : Evaluation of JENDL-2 was performed on the basis of the data measured by Ohkubo et al./1/ among 138 levels measured in the energy region up to 18.6 keV, 116 resonance levels were assumed to be s-wave, and remaining 22 levels were estimated to be p-wave. Neutron widths of all levels were determined from the 2g*(neutron width) measured by Ohkubo et al. However, the value of total spin J for each resonance level was unknown except 13 levels assigned by Ohkubo et al., and the target spin of 2.5 was adopted as J for J-unknown levels. Radiation widths were obtained for 10 levels below 2.6 keV from the measurement by Ohkubo et al. Average radiation width was also estimated to be 328+-18 meV by Ohkubo et al., and was adopted for the other levels. A negative resonance was added at -943 eV so as to reproduce the thermal capture cross section of 480+-10 mb given by Mughabghab et al./2/ For JENDL-3, the total spin J of 125 resonance levels was tentatively estimated with a random number method. Neutron widths of these levels were modified on the basis of the estimated J values. Neutron and radiation widths of the negative resonance level were also modified so as to reproduce the thermal capture cross section according to the above modification of the neutron widths. Scattering radius was taken from the graph (Fig. 1, part A) given by Mughabghab et al. No modification was performed for JENDL-4.0. Unresolved resonance region: 8.468 keV - 860 keV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /3/. 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 6.3698E+00 Elastic 5.8896E+00 n,gamma 4.8020E-01 8.7525E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /3/. 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 /3/. MT= 16 (n,2n) cross section Calculated with POD code /3/. MT= 17 (n,3n) cross section Calculated with POD code /3/. MT= 22 (n,na) cross section Calculated with POD code /3/. MT= 28 (n,np) cross section Calculated with POD code /3/. MT= 32 (n,nd) cross section Calculated with POD code /3/. MT=102 Capture cross section Calculated with POD code /3/. MT=103 (n,p) cross section Calculated with POD code /3/. MT=104 (n,d) cross section Calculated with POD code /3/. MT=105 (n,t) cross section Calculated with POD code /3/. MT=106 (n,He3) cross section Calculated with POD code /3/. MT=107 (n,a) cross section Calculated with POD code /3/. MT=203 (n,xp) cross section Calculated with POD code /3/. MT=204 (n,xd) cross section Calculated with POD code /3/. MT=205 (n,xt) cross section Calculated with POD code /3/. MT=206 (n,xHe3) cross section Calculated with POD code /3/. MT=207 (n,xa) cross section Calculated with POD code /3/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /3/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/3/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/3/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/3/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/3/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/3/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/3/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/3/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/3/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/3/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/3/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/3/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/3/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /3/. 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 /3/. *************************************************************** * Nuclear Model Calculations with POD Code /3/ * *************************************************************** 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 /4/ Protons: Koning and Delaroche /5/ Deuterons: Lohr and Haeberli /6/ Tritons: Becchetti and Greenlees /7/ He-3: Becchetti and Greenlees /7/ Alphas: Lemos /8/ potentials modified by Arthur and Young /9/ 3. Level scheme of Rb- 85 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 5/2 - 1 0.15116 3/2 - 2 0.28099 1/2 - 3 0.51401 9/2 + 4 0.73182 3/2 - 5 0.86898 7/2 - 6 0.88582 1/2 - 7 0.91970 3/2 - 8 0.91971 5/2 - 9 0.95095 5/2 + 10 1.17500 9/2 + 11 1.17553 5/2 - 12 1.29337 13/2 + 13 1.29594 3/2 - 14 1.38421 7/2 - 15 1.44506 7/2 - 16 1.44921 5/2 + 17 1.49629 1/2 - 18 1.63146 5/2 - 19 1.66863 1/2 + 20 1.74780 11/2 + 21 1.78693 5/2 + 22 1.79228 1/2 - 23 1.80220 9/2 + 24 1.85262 3/2 + 25 1.89100 5/2 + 26 1.92970 5/2 - 27 1.95003 1/2 - 28 1.99990 1/2 - 29 2.02811 3/2 - 30 2.03950 1/2 - 31 2.05300 7/2 + 32 2.08760 3/2 - ------------------------- Levels above 2.09760 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /10/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- 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 Rb- 83 10.507 1.317 2.990 0.786 -0.643 7.067 2.056 Kr- 85 11.890 1.302 0.718 0.695 0.285 5.433 2.637 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 Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134 Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261 Br- 81 10.293 1.333 2.879 0.880 -1.411 8.480 1.587 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /11/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) M.Ohkubo et al, J. Nucl. Sci. Technol. 21, 254 (1984). 2) S.F.Mughabghab et al., "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 3) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 4) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 5) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 6) J.M.Lohr, W.Haeberli, Nucl. Phys. A232, 381 (1974). 7) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 8) O.F.Lemos, Orsay Report, Series A, No.136 (1972). 9) E.D.Arthur, P.G.Young, LA-8626-MS (1980). 10) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 11) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).