36-Kr- 85 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-DEC21 20091004 ----JENDL-5 MATERIAL 3646 -----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/MT4,16,17,22,28,32,102-107) added MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonance parameters No resolved resonance region is given. The scattering and capture cross sections are the same as those contained in JENDL-3.3 below 1 keV. Unresolved resonance region: 1 keV - 1 MeV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /1/. 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 7.9765E+00 Elastic 6.2945E+00 n,gamma 1.6608E+00 3.5104E+00 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /1/ above 1 keV. Sum of non-elastic and elastic cross sections below 1 keV. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from total cross sections above 1 keV. A constant value of 6.2557 is assumed below 1 keV. 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 /1/. MT= 16 (n,2n) cross section Calculated with POD code /1/. MT= 17 (n,3n) cross section Calculated with POD code /1/. MT= 22 (n,na) cross section Calculated with POD code /1/. MT= 28 (n,np) cross section Calculated with POD code /1/. MT= 32 (n,nd) cross section Calculated with POD code /1/. MT=102 Capture cross section Calculated with POD code /1/ above 1 keV. The 1/v form was assumed below 1 keV, and the cross section was normalized to 1.66 b at 0.0253 eV./2/ MT=103 (n,p) cross section Calculated with POD code /1/. MT=104 (n,d) cross section Calculated with POD code /1/. MT=105 (n,t) cross section Calculated with POD code /1/. MT=106 (n,He3) cross section Calculated with POD code /1/. MT=107 (n,a) cross section Calculated with POD code /1/. MT=203 (n,xp) cross section Calculated with POD code /1/. MT=204 (n,xd) cross section Calculated with POD code /1/. MT=205 (n,xt) cross section Calculated with POD code /1/. MT=206 (n,xHe3) cross section Calculated with POD code /1/. MT=207 (n,xa) cross section Calculated with POD code /1/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/1/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/1/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/1/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/1/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/1/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 75 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/1/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/1/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/1/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/1/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/1/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/1/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/1/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /1/. 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 /1/. *************************************************************** * Nuclear Model Calculations with POD Code /1/ * *************************************************************** 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 Kr- 85 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 9/2 + 1 0.30487 1/2 - 2 1.10732 1/2 - 3 1.14073 5/2 + 4 1.16669 5/2 + 5 1.22398 5/2 - 6 1.34261 3/2 + 7 1.41657 5/2 + 8 1.43060 1/2 + 9 1.61160 11/2 + 10 1.84700 7/2 + 11 1.87352 5/2 + 12 1.93150 13/2 + 13 1.93883 3/2 - 14 1.99010 9/2 + 15 1.99180 17/2 + 16 2.00440 7/2 + 17 2.05510 3/2 + 18 2.11340 9/2 + 19 2.13510 9/2 + 20 2.13734 5/2 - 21 2.14490 7/2 + 22 2.23520 5/2 - 23 2.38350 7/2 + 24 2.39800 5/2 - 25 2.49790 9/2 - 26 2.51340 9/2 - 27 2.53430 5/2 - 28 2.57370 7/2 - 29 2.59300 5/2 - 30 2.60240 3/2 - 31 2.61790 5/2 - 32 2.63670 11/2 + ------------------------- Levels above 2.64670 MeV are assumed to be continuous. 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 ---------------------------------------------------------- Kr- 86 11.310 2.588 -0.507 0.715 2.085 6.130 3.575 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- 85 10.720 1.302 -0.138 0.819 0.183 6.155 1.944 Br- 84 11.060 0.000 0.608 0.898 -2.409 6.862 0.408 Br- 83 10.507 1.317 1.382 0.813 -0.276 6.734 2.134 Se- 83 12.088 1.317 0.801 0.772 -0.514 6.837 1.331 Se- 82 10.867 2.650 1.071 0.699 1.874 6.455 3.586 Se- 81 10.589 1.333 1.999 0.755 -0.063 6.204 2.253 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /10/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 2) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier (2006). 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) J.Kopecky, M.Uhl, Nucl. Sci. Eng. 41, 1941 (1990).