36-Kr- 84 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-MAY10 20091118 ----JENDL-4.0 MATERIAL 3643 -----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 2.48 keV Evaluation of JENDL-2 was performed as follows : Neutron widths and average radiation width for the two positive levels at 519 and 580 eV were taken from the data given by Mughabghab et al./1/ The six resonance levels from 1.164 to 2.12 keV were abandoned, because their isotopic assignment was uncertain. The value of average radiation width was modified to 121 meV so as to reproduce the neutron resonance capture integral of 2.43+-0.2 barns given by Mughabghab et al. The values of neutron orbital angular momentum L and total spin J were assumed to be 0 and 0.5, respectively. Scattering radius was also taken from the graph (Fig. 1, part A) given by Mughabghab et al. A negative resonance was added at -150 eV so as to reproduce the thermal capture cross section of 0.110+-0.015 barns/1/. For JENDL-3 and -4, any modification was not made, because new measurements have not been carried out. Unresolved resonance region: 2.48 keV - 1 MeV 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 6.3071E+00 Elastic 6.1971E+00 n,gamma 1.1004E-01 2.3895E+00 ---------------------------------------------------------- (*) 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 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 /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=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= 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= 75 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 76 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 77 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 78 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 79 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 80 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 81 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 82 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 83 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 84 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 85 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 86 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 87 (n,n') reaction Neutron angular distributions calculated with POD/2/. MT= 88 (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- 84 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 0.88162 2 + 2 1.83730 0 + 3 1.89778 2 + 4 2.09500 4 + 5 2.34546 4 + 6 2.48920 2 + 7 2.62298 2 + 8 2.70028 3 - 9 2.75928 2 + 10 2.77095 5 - 11 2.77500 2 + 12 2.86109 3 - 13 3.04211 2 + 14 3.08238 3 - 15 3.17251 6 + 16 3.18329 4 + 17 3.21934 5 - 18 3.23602 8 + 19 3.28867 5 + 20 3.31239 3 - 21 3.33500 1 - 22 3.36588 1 - 23 3.40816 3 - 24 3.42673 2 + 25 3.46300 7 + 26 3.47575 1 - 27 3.57000 3 - 28 3.58710 6 - 29 3.63850 5 - 30 3.65147 7 - 31 3.70587 2 + 32 3.71821 3 - 33 3.77700 2 - 34 3.83158 7 - 35 3.87010 3 - 36 3.87880 2 + 37 3.92733 1 - 38 3.95121 6 + ------------------------- Levels above 3.96121 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- 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 Kr- 82 10.867 2.650 2.503 0.781 0.700 8.353 3.187 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 Br- 82 10.599 0.000 2.092 0.832 -2.117 6.154 1.261 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 Se- 80 10.645 2.683 2.442 0.815 0.539 8.768 3.226 ---------------------------------------------------------- 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).