36-Kr- 83 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-MAY10 20091118 ----JENDL-4.0 MATERIAL 3640 -----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 0.272 keV For JENDL-2, parameters were given for 2 positive and a negative resonances on the basis of the data given by Mughabghab et al./1/ Neutron orbital angular momentum L were assumed to be 0. Neutron widths were modified so as to reproduce the thermal capture cross section of 180+-30 barns and the neutron resonance capture integral of 183+-25 barns given by Mughabghab et al. Radiation width of 210 meV for the first level/1/ was adopted for the other resonance levels. However, the values of total spin j were unknown and the target spin of 4.5 was adopted for all the levels. For JENDL-3, the J-values of all resonance levels were tentatively estimated with a random number method. According to modification of the J-values, resonance parameters were also modified so as to reproduce the thermal capture cross section and the neutron resonance capture integral mentioned above. Scattering radius was taken from the graph (fig. 1, Part A) given by Mughabghab et al. In JENDL-4, the radiation width of the negative resonance was changed to 237 meV. Unresolved resonance region: 272 eV - 260 keV The parameters were obtained by fitting to the total and capture cross sections calculated from POD /2/. 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 2.1147E+02 Elastic 9.1343E+00 n,gamma 2.0233E+02 1.5393E+02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with POD code /2/. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross secitons 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 /2/. MT= 16 (n,2n) cross section Calculated with POD code /2/. MT= 17 (n,3n) cross section Calculated with POD code /2/. MT= 22 (n,na) cross section Calculated with POD code /2/. MT= 28 (n,np) cross section Calculated with POD code /2/. MT= 32 (n,nd) cross section Calculated with POD code /2/. MT=102 Capture cross section Calculated with POD code /2/. MT=103 (n,p) cross section Calculated with POD code /2/. MT=104 (n,d) cross section Calculated with POD code /2/. MT=105 (n,t) cross section Calculated with POD code /2/. MT=106 (n,He3) cross section Calculated with POD code /2/. MT=107 (n,a) cross section Calculated with POD code /2/. MT=203 (n,xp) cross section Calculated with POD code /2/. MT=204 (n,xd) cross section Calculated with POD code /2/. MT=205 (n,xt) cross section Calculated with POD code /2/. MT=206 (n,xHe3) cross section Calculated with POD code /2/. MT=207 (n,xa) cross section Calculated with POD code /2/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with POD code /2/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Neutron spectra calculated with POD/2/. MT= 17 (n,3n) reaction Neutron spectra calculated with POD/2/. MT= 22 (n,na) reaction Neutron spectra calculated with POD/2/. MT= 28 (n,np) reaction Neutron spectra calculated with POD/2/. MT= 32 (n,nd) reaction Neutron spectra calculated with POD/2/. MT= 51 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 52 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 53 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 54 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 55 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 56 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 57 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 58 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 59 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 60 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 61 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 62 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 63 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 64 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 65 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 66 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 67 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 68 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 69 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 70 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 71 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 72 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 73 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 74 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 91 (n,n') reaction Neutron spectra calculated with POD/2/. MT= 203 (n,xp) reaction Proton spectra calculated with POD/2/. MT= 204 (n,xd) reaction Deuteron spectra calculated with POD/2/. MT= 205 (n,xt) reaction Triton spectra calculated with POD/2/. MT= 206 (n,xHe3) reaction He3 spectra calculated with POD/2/. MT= 207 (n,xa) reaction Alpha spectra calculated with POD/2/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated with POD code /2/. 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 /2/.*************************************************************** * Nuclear Model Calculations with POD Code /2/ * *************************************************************** 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- 83 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 9/2 + 1 0.00940 7/2 + 2 0.04154 1/2 - 3 0.56202 5/2 - 4 0.57120 3/2 - 5 0.69015 5/2 - 6 0.79890 5/2 + 7 0.81100 3/2 - 8 1.01186 11/2 + 9 1.10000 1/2 - 10 1.10289 9/2 + 11 1.12203 13/2 + 12 1.17040 7/2 - 13 1.22188 5/2 + 14 1.27790 1/2 + 15 1.51680 7/2 + 16 1.52916 9/2 - 17 1.53369 9/2 + 18 1.53810 7/2 - 19 1.64249 9/2 + 20 1.66800 7/2 - 21 1.72161 13/2 + 22 1.73847 11/2 + 23 1.78090 7/2 - 24 1.88890 7/2 - ------------------------- Levels above 1.89890 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- 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 Kr- 81 11.444 1.333 3.305 0.766 -1.104 7.552 1.829 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 Se- 81 10.589 1.333 1.999 0.755 -0.063 6.204 2.253 Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226 Se- 79 10.473 1.350 3.245 0.875 -1.656 8.768 0.729 ---------------------------------------------------------- 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) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 2) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 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).