55-Cs-135 JAEA+ EVAL-Apr09 N.Iwamoto,H.Matsunobu DIST-MAY10 20100119 ----JENDL-4.0 MATERIAL 5531 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 09-04 The resolved resonance parameters were evaluated by H.Matsunobu. The data above the resolved resonance region were evaluated and compiled by N.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 230 eV Resonance parameters of JENDL-3.3 were revised as follows : The resonance energies and neutron widths of 6 levels, and radiation width of the second level (42.2 ev) which were measured by Anufriev et al./1/ were adopted. the rdiation widths of the remaining 5 levels and a negative level were assumed to be 175 meV. The values of total j for the negative and positive 6 levels were estimated by random number method. The neutron width of the negative level was adjusted so as to reproduce the thermal capture cross section of 8.3+-0.3 barns at 0.0253 eV measured by Katoh et al./2/ Unresolved resonance region : 230 eV - 160 keV The unresolved resonance paramters (URP) were determined by ASREP code /3/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code OPTMAN /4/ and CCONE /5/. 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 1.3143e+01 Elastic 4.8408e+00 n,gamma 8.3019e+00 5.3519e+01 n,alpha 1.2909e-14 ---------------------------------------------------------- (*) 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 /5/. MT= 16 (n,2n) cross section Calculated with CCONE code /5/. MT= 17 (n,3n) cross section Calculated with CCONE code /5/. MT= 22 (n,na) cross section Calculated with CCONE code /5/. MT= 24 (n,2na) cross section Calculated with CCONE code /5/. MT= 28 (n,np) cross section Calculated with CCONE code /5/. MT= 29 (n,n2a) cross section Calculated with CCONE code /5/. MT= 30 (n,2n2a) cross section Calculated with CCONE code /5/. MT= 32 (n,nd) cross section Calculated with CCONE code /5/. MT= 33 (n,nt) cross section Calculated with CCONE code /5/. MT= 34 (n,nHe3) cross section Calculated with CCONE code /5/. MT= 41 (n,2np) cross section Calculated with CCONE code /5/. MT= 44 (n,n2p) cross section Calculated with CCONE code /5/. MT= 45 (n,npa) cross section Calculated with CCONE code /5/. MT= 51-91 (n,n') cross section Calculated with CCONE code /5/. MT=102 Capture cross section Calculated with CCONE code /5/. MT=103 (n,p) cross section Calculated with CCONE code /5/. MT=104 (n,d) cross section Calculated with CCONE code /5/. MT=105 (n,t) cross section Calculated with CCONE code /5/. MT=106 (n,He3) cross section Calculated with CCONE code /5/. MT=107 (n,a) cross section Calculated with CCONE code /5/. MT=108 (n,2a) cross section Calculated with CCONE code /5/. MT=111 (n,2p) cross section Calculated with CCONE code /5/. MT=112 (n,pa) cross section Calculated with CCONE code /5/. MT=115 (n,pd) cross section Calculated with CCONE code /5/. MT=116 (n,pt) cross section Calculated with CCONE code /5/. MT=117 (n,da) cross section Calculated with CCONE code /5/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /5/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /5/. MT= 17 (n,3n) reaction Calculated with CCONE code /5/. MT= 22 (n,na) reaction Calculated with CCONE code /5/. MT= 24 (n,2na) reaction Calculated with CCONE code /5/. MT= 28 (n,np) reaction Calculated with CCONE code /5/. MT= 29 (n,n2a) reaction Calculated with CCONE code /5/. MT= 30 (n,2n2a) reaction Calculated with CCONE code /5/. MT= 32 (n,nd) reaction Calculated with CCONE code /5/. MT= 33 (n,nt) reaction Calculated with CCONE code /5/. MT= 34 (n,nHe3) reaction Calculated with CCONE code /5/. MT= 41 (n,2np) reaction Calculated with CCONE code /5/. MT= 44 (n,n2p) reaction Calculated with CCONE code /5/. MT= 45 (n,npa) reaction Calculated with CCONE code /5/. MT= 51-91 (n,n') reaction Calculated with CCONE code /5/. MT=102 Capture reaction Calculated with CCONE code /5/. ***************************************************************** Nuclear Model Calculation with CCONE code /5/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * optical model potential neutron omp: Kunieda,S. et al./6/ (+) proton omp: Koning,A.J. and Delaroche,J.P./7/ deuteron omp: Lohr,J.M. and Haeberli,W./8/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./9/ alpha omp: McFadden,L. and Satchler,G.R./10/ (+) omp parameters were modified. 2) Two-component exciton model/11/ * Global parametrization of Koning-Duijvestijn/12/ was used. * Gamma emission channel/13/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/14/ 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/15/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /16/,/17/ 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 Cs-135 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 7/2 + 1 0.24977 5/2 + 2 0.40803 1/2 + 3 0.60815 5/2 + 4 0.78684 11/2 + 5 0.98140 1/2 + 6 1.06239 1/2 + ------------------- Table 2. Level density parameters -------------------------------------------------------- Nuclide a* Pair Eshell T E0 Ematch 1/MeV MeV MeV MeV MeV MeV -------------------------------------------------------- Cs-136 18.0000 0.0000 -2.9176 0.6768 -1.3925 5.0000 Cs-135 16.6000 1.0328 -1.8144 0.6675 -0.2856 5.6078 Cs-134 17.0000 0.0000 -0.8946 0.7066 -2.2698 5.8956 Cs-133 16.4429 1.0405 -0.1729 0.7096 -1.3562 6.9453 Xe-135 20.2000 1.0328 -3.8043 0.5665 0.4707 4.2857 Xe-134 17.1069 2.0733 -2.8193 0.7693 -0.1097 8.7590 Xe-133 18.7000 1.0405 -1.7673 0.6413 -0.6524 6.0509 Xe-132 16.8500 2.0889 -1.1507 0.6595 0.5201 6.8662 I-134 16.8488 0.0000 -4.8096 0.8747 -2.2475 8.6722 I-133 16.1297 1.0405 -3.5913 0.8275 -1.0073 8.1906 I-132 16.6361 0.0000 -2.4976 0.7769 -2.2437 6.6852 I-131 15.9219 1.0484 -1.6425 0.7356 -0.8231 6.6968 I-130 16.4000 0.0000 -0.6800 0.8536 -4.2325 9.0264 I-129 15.7137 1.0565 -0.1025 0.6848 -0.7998 6.1306 -------------------------------------------------------- Table 3. Gamma-ray strength function for Cs-136 -------------------------------------------------------- * E1: ER = 15.25 (MeV) EG = 4.41 (MeV) SIG = 230.00 (mb) ER = 6.20 (MeV) EG = 2.20 (MeV) SIG = 3.90 (mb) ER = 2.10 (MeV) EG = 5.60 (MeV) SIG = 0.40 (mb) * M1: ER = 7.97 (MeV) EG = 4.00 (MeV) SIG = 1.09 (mb) * E2: ER = 12.25 (MeV) EG = 4.48 (MeV) SIG = 2.96 (mb) -------------------------------------------------------- References 1) Anufriev, V.A. et al.: AE, 63, (5), 346 (1987). 2) Katoh, T. et al.: J. Nucl. Sci. Technol., 34,431 (1997). 3) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 4) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004). 5) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 6) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 7) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003) [Global potential]. 8) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 9) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 10) McFadden,L. and Satchler,G.R.: Nucl. Phys. 84, 177 (1966). 11) Kalbach,C.: Phys. Rev. C33, 818 (1986). 12) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 13) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 14) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 15) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 16) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 17) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).