54-Xe-136 JAEA EVAL-FEB22 S.Kunieda, A.Ichihara, K.Shibata+ DIST-DEC21 20100316 ----JENDL-5 MATERIAL 5461 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-11 Re-evaluation was performed for JENDL-4.0 10-03 Compiled by S.Kunieda 21-11 revised by O.Iwamoto (MF8/MT4,16,17,22,28,32,102-107) 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 490 keV Resonance parameters in JENDL-3.3 consisted of the data measured by Macklin/1/ and by Fogelberg et al./2/. The data of the 1st and 2nd resonance levels are a neutron capture area and a radiation width measured by Macklin. The data of the other levels except the 1st level are g*(neutron width) and the total spin j measured by Fogelberg et al., and contain 4 s-wave levels and 31 p-wave levels. The neutron width of the 1st level at 2154 eV was derived from the neutron capture area using the radiation width of the 2nd level measured by Macklin. The neutron widths of the remaining 35 levels from 18.393 to 480.750 kev were derived using the j-values given by Fogelberg et al. The average radiation width of 122.5 meV was adopted for all the resonance levels except the 1st and 2nd levels. The scattering radius was taken from the graph (fig. 1, Part A) by Mughabghab et al./3/ A negative resonance level was added at -822.03 eV, and the above average radiation width was determined so as to reproduce the thermal capture cross section of 260+-20 mb given by mughabghab et al. In JENDL-4, the energy and neutron width of the negative level were modified so as to reproduce the thermal capture cross section of 130+-15 mb at 0.0253 eV measured by Kondaiah et al./4/ - No unresolved resonance parameters are given. Thermal cross sections & resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 5.42750E+00 Elastic 5.29746E+00 n,gamma 1.30039E-01 8.54723E-02 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. MF= 3 Neutron cross sections MT= 1 Total cross section Sum of partial cross sections. MT= 2 Elastic scattering cross section The OPTMAN /5/ & POD /6/ calculations. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT= 4,51-91 (n,n') cross section The OPTMAN /5/ & POD /6/ calculations. MT= 16 (n,2n) cross section MT= 17 (n,3n) cross section MT= 22 (n,na) cross section MT= 28 (n,np) cross section MT= 32 (n,nd) cross section MT=102 Capture cross section Calculated by the POD code /6/. The value of gamma-ray strength function was determined to follow JENDL-3.3's cross sections around 500 keV. MT=103 (n,p) cross section MT=104 (n,d) cross section MT=105 (n,t) cross section MT=106 (n,He3) cross section MT=107 (n,a) cross section Calculated by the POD code /6/. MT=203 (n,xp) cross section Sum of (n,np) and (n,p) MT=204 (n,xd) cross section Sum of (n,nd) and (n,d) MT=205 (n,xt) cross section MT=206 (n,xHe3) cross section Calculated by the POD code /6/. MT=207 (n,xa) cross section Sum of (n,na) and (n,a) MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering The OPTMAN /5/ & POD /6/ calculations. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction MT= 17 (n,3n) reaction MT= 22 (n,na) reaction MT= 28 (n,np) reaction MT= 32 (n,nd) reaction Neutron spectra calculated by the POD code /6/. MT= 51-90 (n,n') reaction Neutron angular distributions calculated by OPTMAN /5/ & POD /6/. MT= 91 (n,n') reaction Neutron spectra calculated by the POD code /6/. MT= 203 (n,xp) reaction MT= 204 (n,xd) reaction MT= 205 (n,xt) reaction MT= 206 (n,xHe3) reaction MT= 207 (n,xa) reaction Light-ion spectra calculated by the POD code /6/. MF=12 Gamma-ray multiplicities MT= 3 Non-elastic gamma emission Calculated by the POD code /6/. 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 by the POD code /6/. *************************************************************** * Nuclear Model Calculations with POD Code /6/ * *************************************************************** 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 preequilibrium 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. In this evaluation, the OPTMAN code /5/ was employed for neutrons, while the ECIS code /7/ was adopted for charged particles. 2. Optical model & parameters Neutrons: Model: The coupled-channel method based on the rigid-rotor model was adopted. Deformation parameter beta2 was taken from ref./8/ OMP : Coupled-channel optical potential /9/ was applied. Protons: Model: Spherical OMP : Koning and Delaroche /10/ Deuterons: Model: Spherical OMP : Bojowald et al. /11/ Tritons: Mode: Spherical OMP : Becchetti and Greenlees /12/ He-3: Model: Spherical OMP : Becchetti and Greenlees /12/ Alphas: Model: Spherical OMP : A simplified folding model potential /1/ (The nucleon OMP was taken from Ref./9/.) 3. Level scheme of Xe-136 ------------------------------------ No. Ex(MeV) J PI CC ------------------------------------ 0 0.00000 0 + * 1 1.31303 2 + * 2 1.69439 4 + 3 1.89170 6 + 4 2.12569 4 + 5 2.26153 6 + 6 2.28953 2 + 7 2.41475 2 + 8 2.44440 5 + 9 2.46502 4 + 10 2.55988 4 + 11 2.58240 0 + ------------------------------------ Levels above 2.59240 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /13/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- Xe-137 17.403 1.025 -3.891 0.732 -0.237 6.024 1.220 Xe-136 16.658 2.058 -4.823 0.873 0.098 8.676 2.582 Xe-135 17.198 1.033 -3.799 0.704 0.072 5.487 1.968 Xe-134 16.449 2.073 -2.814 0.742 0.503 7.492 2.409 I -136 16.564 0.000 -5.026 0.776 -0.734 4.541 0.579 I -135 15.861 1.033 -5.868 0.979 -0.961 8.260 1.133 I -134 16.358 0.000 -4.805 0.906 -2.236 7.123 0.210 Te-134 16.449 2.073 -7.083 0.955 1.209 7.728 2.398 Te-133 16.992 1.041 -5.785 0.914 -0.835 7.754 0.308 Te-132 16.240 2.089 -4.641 0.884 0.085 8.791 1.925 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /14/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) Macklin, R.L.: ORNL-TM-10766 (1988). 2) Fogelberg, B. et al.: Phys. Rev., C31, 2041 (1985). 3) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 4) Kondaiah, E. et al.: Nucl. Phys., A120, 329 (1968). 5) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 6) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 7) J.Raynal, CEA Saclay report, CEA-N-2772 (1994). 8) S.Raman et al., At. Data and Nucl. Data Tables 78, 1 (1995) 9) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 10) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 11) Bojowald et al., Phys. Rev. C 38, 1153 (1988). 12) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 13) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 14) M.Brink, Ph.D thesis, Oxford University, 1955.