58-Ce-143 JAEA EVAL-JAN10 K.Shibata, T.Nakagawa DIST-MAY10 20100105 ----JENDL-4.0 MATERIAL 5846 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 06-12 Thermal cross sections were determined by T.Nakagawa. 10-01 Statistical model calculations were performed. Data were 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 No resolved resonance parameters are given. The 1/v-shped capture cross section is assumed below 65 eV. At 0.0253 eV, the cross section was normalized to the value of 6.0 b, which was recommended by Mughabghab/1/. Constant scattering cross sections of 4.50 b were assumed below 65 eV. Unresolved resonance region: 65 eV - 500 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 1.0539E+01 Elastic 4.5167E+00 n,gamma 6.0026E+00 1.5924E+01 ---------------------------------------------------------- (*) 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 The cross sections were obtained by subtracting the nonelastic cross sections from the total cross sections. MT= 3 Non-elastic cross section Calculated with POD code /2/. 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= 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 Ce-143 ------------------------- No. Ex(MeV) J PI ------------------------- 0 0.00000 3/2 - 1 0.01890 7/2 - 2 0.04228 5/2 - 3 0.63250 1/2 - 4 0.64030 7/2 - 5 0.66270 9/2 - 6 0.80820 3/2 - 7 0.81700 7/2 + 8 0.86210 1/2 - 9 1.09530 7/2 + 10 1.11680 11/2 - 11 1.15410 3/2 - 12 1.16500 7/2 + 13 1.16760 11/2 + 14 1.17250 1/2 - 15 1.19500 5/2 - 16 1.22000 9/2 - 17 1.29800 5/2 - 18 1.50600 7/2 - 19 1.54200 1/2 - ------------------------- Levels above 1.55200 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 ---------------------------------------------------------- Ce-144 17.495 2.000 1.018 0.558 0.593 6.297 2.221 Ce-143 18.028 1.003 0.415 0.509 0.099 4.421 1.542 Ce-142 17.288 2.014 -0.311 0.573 0.905 6.011 2.810 Ce-141 17.694 1.011 -1.083 0.519 0.478 3.988 2.171 La-143 16.684 1.003 0.848 0.598 -0.544 5.679 1.303 La-142 17.186 0.000 -0.112 0.597 -1.386 4.469 0.432 La-141 16.484 1.011 -0.489 0.648 -0.555 5.963 1.551 Ba-141 17.824 1.011 -0.683 0.618 -0.593 5.852 1.432 Ba-140 17.080 2.028 -1.371 0.619 0.890 6.291 2.522 Ba-139 20.278 1.018 -2.243 0.495 0.501 3.845 2.350 ---------------------------------------------------------- 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) S.F.Mughabghab, Atlas of Neutron Resonances, Elsevier, (2006). 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).