36-Kr- 78 JAEA EVAL-AUG09 K.Shibata, A.Ichihara, S.Kunieda DIST-DEC21 20091118 ----JENDL-5 MATERIAL 3625 -----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/MT4,16,22,28,32,102-107) added 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 0.8 keV Resonance parameters for three positive levels were based on Mughabghab et al./1/ Resonance levels at 0.1719 keV and above 1.136 kev were abandoned, because they belong possibly to Kr-80. The values of neutron orbital angular momentum L and total spin J were assumed to be 0 and 0.5 for all resonance levels, respectively. Scattering radius was also taken from the graph (fig. 1, Part A) given by Mughabghab et al. A negative resonance was added so as to reproduce the thermal capture cross section of 6.2+-0.9 barns given by Mughabghab et al. In JENDL-4, the radiation width of the negative resonance was changed to 169.4 meV so as to reproduce the thermal capture cross section measured by Kondaiah et al./2/ Unresolved resonance region: 800 eV - 1 MeV 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 1.2613E+01 Elastic 7.8806E+00 n,gamma 4.7322E+00 2.6355E+01 ---------------------------------------------------------- (*) 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= 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= 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= 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 Kr- 78 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 0 + 1 0.45504 2 + 2 1.01718 0 + 3 1.11947 4 + 4 1.14792 2 + 5 1.56476 3 + 6 1.65390 4 + 7 1.75586 2 + 8 1.77293 2 + 9 1.87290 4 + 10 1.97782 6 + 11 2.00742 1 - ------------------------- Levels above 2.01742 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 ---------------------------------------------------------- Kr- 79 11.220 1.350 3.562 0.809 -1.546 8.309 1.475 Kr- 78 10.422 2.717 2.928 0.913 -0.557 10.634 2.007 Kr- 77 10.995 1.368 3.100 0.851 -1.709 8.732 1.312 Kr- 76 10.198 2.753 2.460 0.926 -0.300 10.443 1.222 Br- 78 10.399 0.000 3.911 0.857 -3.042 7.363 0.648 Br- 77 9.864 1.368 3.789 0.924 -1.983 9.420 1.305 Br- 76 10.177 0.000 3.445 0.865 -2.801 7.086 0.688 Se- 76 10.198 2.753 3.354 0.862 0.003 9.763 3.009 Se- 75 10.143 1.386 3.710 0.930 -2.266 9.803 1.432 Se- 74 9.973 2.790 3.042 0.831 0.606 8.936 2.903 ---------------------------------------------------------- 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) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 2) Kondaiah, E. et al.: Nucl. Phys., A120, 329 (1968). 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).