44-Ru-102 JNDC EVAL-MAR90 JNDC FP NUCLEAR DATA W.G. DIST-MAY10 20091209 ----JENDL-4.0 MATERIAL 4443 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT =========================================================== 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/. 09-12 JENDL-4.0. Compiled by A.Ichihara (jaea/ndc). ***** modified parts for JENDL-4.0 ******************* (2,151) Resolved resonance parameters were revised by T.Nakagawa. (2,151) Unresolved resonance parameters were updated. ********************************************************** mf = 1 General information mt=451 Comments and dictionary mf = 2 Resonance parameters mt=151 Resolved and unresolved resonance parameters Resolved resonance region (MLBW formula) : below 13.4 keV JENDL-3.3 was adopted, and parameters of a negative resonance were modified so as to repruduce the thermal total cross setion of 10.4+-0.6 b/3/, capture cross section of 1.48+- 0.16 b/4,5,6/. The data of Ishikawa/5/ was multiplied by a factor of 1.26, because standard cross section of Ru-96(n,g) has changed from 0.21 b to 0.27 b. Scattering radius of 6.6 fm was assumed from its systematics/7/. ** comments to JENDL-3.3 ** Resonance parameters of JENDL-2/1/ were modified according to new experimental data. For JENDL-2, resonance energies below 2.5 keV were taken from the data of Priesmeyer and Jung/8/ and Shaw et al./9/, and for the other resonances above 2.7 keV from Macklin and Halperin/10/. The neutron and radiation widths of large resonances were taken from Priesmeyer and Jung/8/ and Macklin and Halperin/10/. For others, the average radiation width of 0.112+-0.027 eV was adopted. For levels observed by Shaw et al. and for three fictitious levels at 2.467, 2.556 and 2.645 keV, the parameters were determined by assuming S0=0.43e-4, D0=340 ev, S1=4.1e-4 and D1=110 eV. Parameters of the negative level added at -146 eV and the first positive level were adjusted to reproduce the capture cross section of 1.21 +-0.07 barns at 0.0253 eV and its resonance integral of 4.2 +-0.1 barns/11/. For JENDL-3, neutron and radiation widths of 14 resonances were reevaluated on the basis of the experimental data of Anufriev et al./12/ For the resonances observed by Shaw et al., reduced neutron widths were given as 6.5 meV and 65 meV for s-wave and p-wave resonances, respectively. Parameters of the negative resonance were also revise. Scattering radius was modified from 6.35 fm to 6.1 fm based on the systematics. Neutron orbital angular momentum L of some resonances was estimated with a method of Bollinger and Thomas/13/. Unresolved resonance region : 13.4 keV - 300 keV Unresolved resonance parameters were adopted from JENDL-2. The neutron strength functions, S0, S1 and S2 were calculated with optical model code CASTHY/14/. 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. Typical values of the parameters at 70 keV: S0 = 0.450e-4, S1 = 5.000e-4, S2 = 0.530e-4, Sg = 3.61e-4, Gg = 0.115 eV, R = 5.756 fm. The unresolved resonance parameters were calculated using the ASREP code/15/. The parameters should be used only for self-shielding calculation. Thermal cross sections and resonance integrals at 300K (b) ------------------------------------------------------- 0.0253 eV reson. integ.(*) ------------------------------------------------------- total 10.408 elastic 8.932 capture 1.475 4.41 ------------------------------------------------------- (*) In the energy range from 0.5 eV to 10 MeV. mf = 3 Neutron cross sections Below 13.4 keV, resolved resonance parameters were given. 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/16/ standing on a preequilibrium and multi-step evaporation model. The OMP's for neutron given in Table 1 were determined to reproduce a systematic trend of the total cross section by changing rso of Iijima-Kawai potential/17/. The OMP's for charged particles are as follows: proton = Perey/18/ alpha = Huizenga and Igo/19/ deuteron = Lohr and Haeberli/20/ helium-3 and triton = Becchetti and Greenlees/21/ Parameters for the composite level density formula of Gilbert and Cameron/22/ were evaluated by Iijima et al./23/ 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 /24/. mt = 1 Total Spherical optical model calculation was adopted. 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./25/. no. energy(MeV) spin-parity dwba cal. gr. 0.0 0 + 1 0.4751 2 + * 2 0.9437 0 + 3 1.1032 2 + 4 1.1064 4 + 5 1.5217 3 + 6 1.5806 2 + 7 1.6027 4 + 8 1.7987 4 + 9 1.8371 0 + 10 1.8732 6 + 11 2.0369 2 + 12 2.0442 3 - * 13 2.2192 5 + 14 2.2612 2 + 15 2.3720 5 - 16 2.4211 4 + 17 2.4419 4 + Levels above 2.5 MeV were assumed to be overlapping. For the levels with an asterisk, the contribution of direct inelastic scattering cross sections was calculated by the DWUCK-4 code/26/. Deformation parameters (beta2 = 0.2443 and beta3 = 0.196) were based on the data compiled by Raman et al./27/ and Spear/28/, respectively. 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/29/ and normalized to 1 milli-barn at 14 MeV. The gamma-ray strength function (3.44e-04) was adjusted to reproduce the capture cross section of 110 milli-barns at 70 keV measured by Macklin et al./30,31/ 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 =103 (n,p) cross section mt =104 (n,d) cross section mt =105 (n,t) 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 (= 72.0) was estimated by the formula derived from Kikuchi-Kawai's formalism/32/ 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) 16.70 mb (systematics of Forrest/33/) (n,alpha) 6.20 mb (recommended by Forrest/33/) 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. Contribution of direct inelastic scattering was calculated with DWUCK-4. For other reactions, isotropic distributions 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 from overlapping levels and for other neutron emitting reactions. TABLE 1 NEUTRON OPTICAL POTENTIAL PARAMETERS DEPTH (MEV) RADIUS(FM) DIFFUSENESS(FM) ---------------------- ------------ --------------- V = 47.5 R0 = 5.972 A0 = 0.62 WS = 9.74 RS = 6.594 AS = 0.35 VSO= 7.0 RSO= 5.97 ASO= 0.62 THE FORM OF SURFACE ABSORPTION PART IS DER. WOODS-SAXON TYPE. TABLE 2 LEVEL DENSITY PARAMETERS NUCLIDE A(1/MEV) T(MEV) C(1/MEV) EX(MEV) PAIRING --------------------------------------------------------------- 42-MO- 98 1.594E+01 6.900E-01 7.358E-01 7.888E+00 2.570E+00 42-MO- 99 1.774E+01 6.200E-01 4.294E+00 6.058E+00 1.280E+00 42-MO-100 1.780E+01 6.000E-01 6.702E-01 6.645E+00 2.220E+00 42-MO-101 2.085E+01 5.650E-01 7.153E+00 6.092E+00 1.280E+00 43-TC- 99 1.600E+01 6.550E-01 2.973E+00 5.984E+00 1.290E+00 43-TC-100 1.637E+01 5.850E-01 1.189E+01 3.635E+00 0.0 43-TC-101 1.675E+01 6.440E-01 6.361E+00 5.761E+00 9.400E-01 43-TC-102 1.761E+01 5.400E-01 1.217E+01 3.317E+00 0.0 44-RU-100 1.520E+01 7.200E-01 7.835E-01 8.078E+00 2.570E+00 44-RU-101 1.726E+01 6.700E-01 7.228E+00 6.836E+00 1.280E+00 44-RU-102 1.643E+01 6.550E-01 8.872E-01 7.106E+00 2.220E+00 44-RU-103 1.890E+01 6.480E-01 1.210E+01 7.110E+00 1.280E+00 --------------------------------------------------------------- Spin cutoff parameters were calculated as 0.146*sqrt(a)*a**(2/3). 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