59-Pr-141 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G. DIST-MAY10 20091214 ----JENDL-4.0 MATERIAL 5925 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT =========================================================== Resonance parameters in JENDL-3.3 were revised for JENDL-4. =========================================================== =========================================================== JENDL-3.2 data were automatically transformed to JENDL-3.3. Interpolation of spectra: 22 (unit base interpolation) (3,251) deleted, T-matrix of (4,2) deleted, and others. =========================================================== History 84-10 Evaluation for JENDL-2 was made by JNDC FPND W.G./1/ 90-03 Modification for JENDL-3 was made/2/. 93-10 JENDL-3.2 was made by JNDC FPND W.G. ***** modified parts for JENDL-3.2 ******************** (2,151) Resolved resonance parameters *********************************************************** 10-03 JENDL-4.0 was made. Resoloved resonance parameters were evaluated by T.Nakagawa. Unresolved resonance parameters were evaluated by S.Kunieda. The LSSF=1 was applied. Compiled by S.Kunieda ***** modified parts for JENDL-4.0 ******************** (1,451) Updated. (2,151) Updated. (3,1) Re-calculated from partial cross sections. (3,2) Calculated from URP in lower energy range. (3,4) Re-calculated from partial cross sections. (3,102) Calculated from URP in lower energy range. *********************************************************** mf = 1 General information mt=451 Comments and dictionary mf = 2 Resonance parameters mt=151 Resolved and unresolved resonance parameters Resolved resonance parameters for MLBW formula (below 13.226keV) Resonance parameters were taken from JENDL-2/3/ and slightly modified. In the evaluation for JENDL-2, neutron widths were evaluated on the basis of Wynchank et al./4/, Morgenstern et al./5/ and Taylor et al./6/ radiation widths were determined from capture areas measured by Taylor et al. For the levels whose capture aria was only the existing data, their neutron widths were deduced by assuming the average radiation width of 0.084+- 0.024 eV. Scattering radius of 4.9 fm was adopted from Mughabghab et at./7/ For JENDL-3, parameters of a negative resonance were modified so as to reproduce the capture cross section of 11.5+-0.3 barns at 0.0253 eV/7/ and the total cross section measured by Zimmerman et al./8/ and Hickman/9/. Total spin J of some resonances was tentatively estimated with a random number method. For JENDL-3.2, these resonance parameters were modified so as to reproduce the capture area data measured at ORNL, by taking account of the correction factor of 1.0737 announced by Allen et al./10/. ************************************************************** For JENDL-4.0, total spin J of 1364- and 3928-eV levels were modified on the basis of Alfimenkov et al./30/ Average capture cross section of 11.47+-0.29 b at 0.0253 eV was obtained from experimental data/8,31-35/. The parameters of -30-eV level were modified to reproduce the average cross section and the elastic scattering of 2.71+-0.06 b/36/. ************************************************************** Unresolved resonance region : 13.226 keV - 100 keV The neutron strength function S0 was based on the compilation of Mughabghab et al., and S1 and S2 were calculated with optical model code CASTHY/11/. The observed level spacing was determined to reproduce the capture cross section calculated with CASTHY. The effective scattering radius was obtained from fitting to the calculated total cross section at 100 keV. The radiation width Gg was based on the systematics of measured values for neighboring nuclides. Typical values of the parameters at 70 keV: S0 = 1.500e-4, S1 = 1.200e-4, S2 = 1.500e-4, Sg = 6.06e-4, Gg = 0.086 eV, R = 5.181 fm. *************************************************************** For JENDL-4.0, the unresolved resonance parameters were re-evaluated by the ASREP /37/ code so as to reproduce the total and capture cross sections given in JENDL3.3 in the energy region from 13.226 keV to 160 keV. The parameters should be used only for self-shielding calculations. *************************************************************** Thermal cross sections & resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 1.42103E+01 Elastic 2.72998E+00 n,gamma 1.14803E+01 1.83683E+01 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. mf = 3 Neutron cross sections Below 100 keV, resonance parameters were given. Above 100 keV, the spherical optical and statistical model calculation was performed with CASTHY, by taking account of competing reactions, of which cross sections were calculated with PEGASUS/12/ standing on a preequilibrium and multi-step evaporation model. The OMP's for neutron given in Table 1 were adopted from Moldauer/13/ since the parameters reproduced well the total cross section measured by Foster and Glasgow/14/. The OMP's for charged particles are as follows: proton = Perey/15/ alpha = Huizenga and Igo/16/ deuteron = Lohr and Haeberli/17/ helium-3 and triton = Becchetti and Greenlees/18/ Parameters for the composite level density formula of Gilbert and Cameron/19/ were evaluated by Iijima et al./20/ More extensive determination and modification were made in the present work. Table 2 shows the level density parameters used in the present calculation. Energy dependence of spin cut-off parameter in the energy range below E-joint is due to Gruppelaar /21/. mt = 1 Total Below 5 MeV, spherical optical model calculation was adopted. Above 5 MeV, eye-guiding was made on the basis of the data measured by Foster and Glasgow/14/. mt = 2 Elastic scattering Calculated as (total - sum of partial cross sections). mt = 4, 51 - 91 Inelastic scattering Spherical optical and statistical model calculation was adopted. The level scheme was taken from Ref./22/. no. energy(MeV) spin-parity gr. 0.0 5/2 + 1 0.1454 7/2 + 2 1.1180 11/2 - 3 1.1270 3/2 + 4 1.2927 5/2 + 5 1.2986 1/2 + 6 1.4350 3/2 + 7 1.4502 7/2 + 8 1.4561 5/2 - Levels above 1.48 MeV were assumed to be overlapping. mt = 102 Capture Spherical optical and statistical model calculation with CASTHY was adopted. Direct and semi-direct capture cross sections were estimated according to the procedure of Benzi and Reffo/23/ and normalized to 1 milli-barn at 14 MeV. The gamma-ray strength function (6.38e-04) was adjusted to the capture cross section of 110 milli-barns at 30 keV measured by Musgrove et al./24/ The results were modified by multipling with an energy dependent factor to reproduce well the experi- mental data such as those measured by Zaikin et al./25/ and Stupegia et al./26/ mt = 16 (n,2n) cross section mt = 17 (n,3n) cross section mt = 22 (n,n'a) cross section mt = 28 (n,n'p) cross section mt = 32 (n,n'd) cross section mt = 33 (n,n't) cross section 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,alpha) cross section These reaction cross sections were calculated with the preequilibrium and multi-step evaporation model code PEGASUS. The Kalbach's constant k (= 314.1) was estimated by the formula derived from Kikuchi-Kawai's formalism/27/ and level density parameters. Finally, the (n,p) and (n,alpha) cross sections were normalized to the following values at 14.5 MeV: (n,p) 9.50 mb (recommended by Rorrest/28/) (n,alpha) 3.00 mb (recommended by Rorrest) The (n,2n) cross section was determined by eye-guiding of the data measured by Bormann et al./29/. The (n,alpha) cross section below 13.225 keV was calculated from resonance parameters, by assuming a mean alpha width of 1.15e-8 eV so as to reproduce the thermal cross section/7/. The cross section was averaged in suitable energy intervals. Above 13.225 keV, the cross section was connected smoothly to the PEGASUS calculation. mt = 251 mu-bar Calculated with CASTHY. mf = 4 Angular distributions of secondary neutrons Legendre polynomial coefficients for angular distributions are given in the center-of-mass system for mt=2 and discrete inelas- tic levels, and in the laboratory system for mt=91. They were calculated with CASTHY. For other reactions, isotropic distri- butions in the laboratory system were assumed. mf = 5 Energy distributions of secondary neutrons Energy distributions of secondary neutrons were calculated with PEGASUS for inelastic scattering to overlapping levels and for other neutron emitting reactions. TABLE 1 NEUTRON OPTICAL POTENTIAL PARAMETERS DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM) ---------------------- ------------ --------------- V = 46.0 R0 = 6.638 A0 = 0.62 WS = 7.0 RS = 6.638 AS = 1.0 VSO= 7.0 RSO= 6.638 ASO= 0.62 THE FORM OF SURFACE ABSORPTION PART IS GAUSSIAN TYPE. TABLE 2 LEVEL DENSITY PARAMETERS NUCLIDE SYST A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING --------------------------------------------------------------- 57-LA-137 1.558E+01 6.210E-01 3.521E+00 4.624E+00 7.000E-01 57-LA-138 1.450E+01 6.310E-01 7.202E+00 3.634E+00 0.0 57-LA-139 1.380E+01 6.500E-01 1.653E+00 4.468E+00 8.500E-01 57-LA-140 1.558E+01 5.900E-01 7.912E+00 3.425E+00 0.0 58-CE-138 * 1.618E+01 5.580E-01 2.611E-01 5.011E+00 1.870E+00 58-CE-139 1.374E+01 6.450E-01 9.282E-01 4.685E+00 1.170E+00 58-CE-140 1.413E+01 6.541E-01 3.376E-01 5.852E+00 2.020E+00 58-CE-141 1.714E+01 5.150E-01 7.134E-01 3.957E+00 1.170E+00 59-PR-139 * 1.630E+01 5.556E-01 2.158E+00 3.843E+00 7.000E-01 59-PR-140 1.448E+01 6.430E-01 7.927E+00 3.814E+00 0.0 59-PR-141 1.400E+01 6.500E-01 1.810E+00 4.559E+00 8.500E-01 59-PR-142 1.595E+01 6.150E-01 1.201E+01 3.974E+00 0.0 --------------------------------------------------------------- syst: * = ldp's were determined from systematics. 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