54-Xe-134 JAEA EVAL-FEB22 S.Kunieda, A.Ichihara, K.Shibata+ DIST-DEC21 20100316 ----JENDL-5 MATERIAL 5455 -----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/MT4,16,17,22,28,102-104,107) JENDL/AD-2017 adopted (MF8/MT32,105,106) added (MF9/MT102,107) JENDL/AD-2017 adopted (MF10/MT16) JENDL/AD-2017 based 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 10.3 keV Resonance parameters of JENDL-3.3 consisted of 1 point data measured at 1000.6 eV by Ribon et al./1/ and neutron capture area data measured at 2186, 6315, 7260, and 9383 eV by Macklin /2/. The 1st level data given by Ribon were (abundance)*g*(neutron width); this neutron width was derived by using abundance (10.44 %) and g=1. The neutron widths based on the area data were derived by assuming average radiation width larger than area data and g=1. This average radiation width was estimated to be 450 meV, and adopted also for the 1st level. The neutron orbital angular momentum l was assumed to be 0 for all resonance levels. A negative resonance level was added at -100 ev so as to reproduce the thermal capture cross section of 265+-20 mb measured by Kondaiah et al./3/. The scattering radius was taken from the graph (fig. 1, Part A) given by Mughabghab et al./4/. In JENDL-4, errors of input data were only modified. - Unresolved resonance region: 10.3 keV - 250 keV The parameters were obtained by fitting to the total and capture cross sections calculated by the POD code /5/. The ASREP code /6/ was employed in this evaluation. The unresolved parameters should be used only for self-shielding calculation. Thermal cross sections & resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 3.99976E+00 Elastic 3.73469E+00 n,gamma 2.65070E-01 5.95524E-01 ---------------------------------------------------------- (*) 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 /7/ & POD /5/ calculations. MT= 3 Non-elastic cross section Sum of partial non-elastic cross sections. MT= 4,51-91 (n,n') cross section The OPTMAN /7/ & POD /5/ 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 Calculated by the POD code /5/. MT=102 Capture cross section Calculated by the POD code /5/. The value of gamma-ray strength function was determined to reproduce experimental capture cross sections measured by Beer et al /8/. 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 /5/. 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 /5/. 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 /7/ & POD /5/ 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 /5/. MT= 51-90 (n,n') reaction Neutron angular distributions calculated by OPTMAN /7/ & POD /5/. MT= 91 (n,n') reaction Neutron spectra calculated by the POD code /5/. 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 /5/. 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 /5/. *************************************************************** * Nuclear Model Calculations with POD Code /5/ * *************************************************************** 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 /7/ was employed for neutrons, while the ECIS code /9/ 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./10/ OMP : Coupled-channel optical potential /11/ was applied. Protons: Model: Spherical OMP : Koning and Delaroche /12/ Deuterons: Model: Spherical OMP : Bojowald et al. /13/ Tritons: Mode: Spherical OMP : Becchetti and Greenlees /14/ He-3: Model: Spherical OMP : Becchetti and Greenlees /14/ Alphas: Model: Spherical OMP : A simplified folding model potential /2/ (The nucleon OMP was taken from Ref./11/.) 3. Level scheme of Xe-134 ------------------------------------ No. Ex(MeV) J PI CC ------------------------------------ 0 0.00000 0 + * 1 0.84704 2 + * 2 1.61377 2 + 3 1.73116 4 + * 4 1.91960 3 + 5 1.96550 7 - 6 2.13661 5 + 7 2.27201 4 + 8 2.30225 4 + 9 2.35297 4 + 10 2.40850 5 + ------------------------------------ Levels above 2.41850 MeV are assumed to be continuous. 4. Level density parameters Energy-dependent parameters of Mengoni-Nakajima /15/ were used ---------------------------------------------------------- Nuclei a* Pair Esh T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV ---------------------------------------------------------- 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 Xe-133 16.992 1.041 -1.762 0.696 -0.731 6.456 0.911 Xe-132 16.240 2.089 -1.146 0.723 0.006 8.026 2.425 I -134 16.358 0.000 -4.805 0.906 -2.236 7.123 0.210 I -133 15.660 1.041 -3.586 0.875 -1.279 8.089 2.025 I -132 16.152 0.000 -2.493 0.768 -1.905 5.957 0.162 Te-132 16.240 2.089 -4.641 0.884 0.085 8.791 1.925 Te-131 22.166 1.048 -3.417 0.613 -0.582 5.846 1.043 Te-130 16.030 2.105 -2.605 0.776 0.213 8.078 1.815 ---------------------------------------------------------- 5. Gamma-ray strength functions M1, E2: Standard Lorentzian (SLO) E1 : Generalized Lorentzian (GLO) /16/ 6. Preequilibrium process Preequilibrium is on for n, p, d, t, He-3, and alpha. Preequilibrium capture is on. References 1) Ribon, P. et al.: CEA-N-1149 (1969). 2) Macklin, R.L.: ORNL-TM-10766 (1988). 3) Kondaiah, E. et al.: Nucl. Phys., A120, 329 (1968). 4) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 5) A.Ichihara et al., JAEA-Data/Code 2007-012 (2007). 6) Y.Kikuchi et al., JAERI-Data/Code 99-025 (1999) [in Japanese]. 7) E.Soukhovitski et al., JAERI-Data/Code 2005-002 (2005). 8) H.Beer et al., NEANDC(E)-252U,5,8406 (1984). 9) J.Raynal, CEA Saclay report, CEA-N-2772 (1994). 10) S.Raman et al., At. Data and Nucl. Data Tables 78, 1 (1995) 11) S.Kunieda et al., J. Nucl. Sci. Technol. 44, 838 (2007). 12) A.J.Koning, J.P.Delaroche, Nucl. Phys. A713, 231 (2003). 13) Bojowald et al., Phys. Rev. C 38, 1153 (1988). 14) F.D.Becchetti,Jr., G.W.Greenlees, "Polarization Phenomena in Nuclear Reactions," p.682, The University of Wisconsin Press (1971). 15) A.Mengoni, Y.Nakajima, J. Nucl. Sci. Technol. 31, 151 (1994). 16) M.Brink, Ph.D thesis, Oxford University, 1955.