46-Pd-107 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata DIST-DEC21 20100119 ----JENDL-5 MATERIAL 4640 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-12 The resolved resonance parameters were evaluated by K.Shibata. The data above the resolved resonance region were evaluated and compiled by N.Iwamoto. 20-01 The resolved resonance parameters were revised by N.Iwamoto. 21-11 revised by O.Iwamoto (MF8/MT4,16,17,22,24,28,32,41,102-107) 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 1.0 keV For JENDL-2, resonance energies were based on the data by Macklin/1/. Neutron widths were taken from experimental data of Singh et al./2/ and Macklin/1/. The average radiation width of 0.125 eV/2/ was assumed. For jendl-3, the resonance energies were adopted from JENDL-2. Neutron widths were taken from the measurement of Anufriev et al./3/ or determined from the capture area data measured by Macklin/4/ and an averaged radiation width of 131+-69 meV. Radiation widths of resonances whose neutron width was measured by Anufriev et al. were determined from the data of the capture area measured by Macklin/4/ and the neutron width/3/. Total spin j of some resonances was tentatively estimated with a random number method. Neutron orbital angular momentum l of some resonances was estimated with a method of Bollinger and Thomas/5/. A negative resonance was adjusted to so as to be consistent with the lower-limit of the thermal capture cross section measured by Nakamura et al./6/ ** for JENDL-5alpha2 ************************************** The neutron width of negative resonance was adjusted to reproduce the data of Terada et al. (Prog. Nucl. Eng., 82, 118 (2015)). The 3.9 and 5.2-eV resonances were removed (Nucl. Data Sheets 119, 143 (2014)). *********************************************************** Unresolved resonance region : 1.0 keV - 100 keV The unresolved resonance paramters (URP) were determined by ASREP code /7/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code OPTMAN /8/ and CCONE /9/. 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. (*) (barn) (barn) ---------------------------------------------------------- Total 1.2706e+01 Elastic 3.4638e+00 n,gamma 9.2426e+00 1.1287e+02 n,alpha 1.1738e-06 ---------------------------------------------------------- (*) 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 Obtained by subtracting non-elastic scattering cross sections from total cross section. MT= 4 (n,n') cross section Calculated with CCONE code /9/. MT= 16 (n,2n) cross section Calculated with CCONE code /9/. MT= 17 (n,3n) cross section Calculated with CCONE code /9/. MT= 22 (n,na) cross section Calculated with CCONE code /9/. MT= 24 (n,2na) cross section Calculated with CCONE code /9/. MT= 28 (n,np) cross section Calculated with CCONE code /9/. MT= 32 (n,nd) cross section Calculated with CCONE code /9/. MT= 41 (n,2np) cross section Calculated with CCONE code /9/. MT= 51-91 (n,n') cross section Calculated with CCONE code /9/. MT=102 Capture cross section Calculated with CCONE code /9/. MT=103 (n,p) cross section Calculated with CCONE code /9/. MT=104 (n,d) cross section Calculated with CCONE code /9/. MT=105 (n,t) cross section Calculated with CCONE code /9/. MT=106 (n,He3) cross section Calculated with CCONE code /9/. MT=107 (n,a) cross section Calculated with CCONE code /9/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /9/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /9/. MT= 17 (n,3n) reaction Calculated with CCONE code /9/. MT= 22 (n,na) reaction Calculated with CCONE code /9/. MT= 24 (n,2na) reaction Calculated with CCONE code /9/. MT= 28 (n,np) reaction Calculated with CCONE code /9/. MT= 32 (n,nd) reaction Calculated with CCONE code /9/. MT= 41 (n,2np) reaction Calculated with CCONE code /9/. MT= 51-91 (n,n') reaction Calculated with CCONE code /9/. MT=102 Capture reaction Calculated with CCONE code /9/. ***************************************************************** Nuclear Model Calculation with CCONE code /9/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * coupled channels calculation coupled levels: 0,4 (see Table 1) * optical model potential neutron omp: Kunieda,S. et al./10/ (+) proton omp: Koning,A.J. and Delaroche,J.P./11/ deuteron omp: Lohr,J.M. and Haeberli,W./12/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./13/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./13/ alpha omp: Huizenga,J.R. and Igo,G./14/ (+) omp parameters were modified. 2) Two-component exciton model/15/ * Global parametrization of Koning-Duijvestijn/16/ was used. * Gamma emission channel/17/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/18/ was applied. * Neutron, proton, deuteron, triton, He3, alpha and gamma decay channel were taken into account. * Transmission coefficients of neutrons were taken from optical model calculation. * The level scheme of the target is shown in Table 1. * Level density formula of constant temperature and Fermi-gas model were used with shell energy correction/19/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /20/,/21/ was used for E1 transition. For M1 and E2 transitions the standard Lorentzian form was adopted. The prameters are shown in Table 3. ------------------------------------------------------------------ Tables ------------------------------------------------------------------ Table 1. Level Scheme of Pd-107 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 5/2 + * 1 0.11574 1/2 + 2 0.21460 11/2 - 3 0.30278 5/2 + 4 0.31220 7/2 + * 5 0.34818 5/2 + 6 0.36680 7/2 + 7 0.38180 3/2 + 8 0.39242 7/2 + 9 0.41200 1/2 + 10 0.47121 3/2 + ------------------- *) Coupled levels in CC calculation Table 2. Level density parameters -------------------------------------------------------- Nuclide a* Pair Eshell T E0 Ematch 1/MeV MeV MeV MeV MeV MeV -------------------------------------------------------- Pd-108 14.3000 2.3094 3.1785 0.6359 0.3436 6.8413 Pd-107 15.0000 1.1601 3.1932 0.6723 -1.5375 6.6188 Pd-106 14.4000 2.3311 2.3412 0.6736 0.1590 7.3089 Pd-105 14.9000 1.1711 2.0672 0.7067 -1.5220 6.8969 Rh-107 13.0075 1.1601 4.0295 0.7116 -1.4170 6.5036 Rh-106 14.2000 0.0000 3.7991 0.5945 -1.6674 4.0000 Rh-105 15.8000 1.1711 3.4219 0.6193 -1.2405 6.1130 Rh-104 14.1000 0.0000 2.9724 0.6799 -2.3482 5.1092 Ru-106 13.4840 2.3311 4.1609 0.6686 0.0022 7.2594 Ru-105 15.3000 1.1711 4.2450 0.6623 -1.8991 6.8479 Ru-104 13.2688 2.3534 3.6273 0.6755 0.1955 7.1592 Ru-103 14.0500 1.1824 3.5429 0.7267 -1.9541 7.2112 Ru-102 14.0000 2.3764 2.6482 0.6699 0.2865 7.1898 -------------------------------------------------------- Table 3. Gamma-ray strength function for Pd-108 -------------------------------------------------------- * E1: ER = 15.92 (MeV) EG = 7.18 (MeV) SIG = 199.00 (mb) * M1: ER = 8.61 (MeV) EG = 4.00 (MeV) SIG = 1.17 (mb) * E2: ER = 13.23 (MeV) EG = 4.81 (MeV) SIG = 2.42 (mb) -------------------------------------------------------- References 1) Macklin, R.L.: private communication (1984). 2) Singh, U.N., et al.: Nucl. Sci. Eng., 67, 54 (1978). 3) Anufriev, V.A. et al.: Proc Fifth All Union Conf on Neutron Physics, Kiev, Sept. 1980, Vol. 2, 159 (1980). 4) Macklin, R.L. : Nucl. Sci. Eng., 89, 79 (1985). 5) Bollinger, L.M., Thomas, G.E.: Phys. Rev., 171,1293(1968). 6) Nakamura, S., et al.: J. Nucl. Sci. Technol., 44, 103 (2007). 7) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 8) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004). 9) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 10) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 11) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003) [Global potential]. 12) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 13) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 14) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962). 15) Kalbach,C.: Phys. Rev. C33, 818 (1986). 16) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 17) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 18) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 19) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 20) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 21) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).