50-Sn-117 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata DIST-DEC21 20100119 ----JENDL-5 MATERIAL 5040 -----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. 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 2.35 keV In JENDL-3.3, resonance parameters were mainly based on Mughabghab et al./1/ Data measured by Alfimenkov et al. /2/ were also considered. 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/3/. Averaged radiation width of 74 meV was deduced and applied to the levels whose radiation width was unknown. Scattering radius of 6.1 fm was assumed from the systematics of measured values for neighboring nuclides. A negative resonance was added so as to reproduce the thermal capture and scattering cross sections given by Mughabghab et al. In JENDL-4, the data below 1488.5 eV were replaced with the ones obtained by Smith et al./4/ Some of the J values are based on the work of Georigiev et al./5/ The remaining unknow J values were estimated by a random number method. The parameters for a negative resonance were adjusted so as to reproduce the thermal capture cross section recommended by Mughabghab /6/. Unresolved resonance region : 2.35 keV - 200 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 5.9238e+00 Elastic 4.8434e+00 n,gamma 1.0804e+00 1.7943e+01 n,alpha 3.2060e-08 ---------------------------------------------------------- (*) 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: Kunieda,S. et al./10/ deuteron omp: Lohr,J.M. and Haeberli,W./11/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./12/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./12/ alpha omp: Huizenga,J.R. and Igo,G./13/ (+) omp parameters were modified. 2) Two-component exciton model/14/ * Global parametrization of Koning-Duijvestijn/15/ was used. * Gamma emission channel/16/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/17/ 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/18/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /19/,/20/ 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 Sn-117 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 1/2 + * 1 0.15856 3/2 + 2 0.31458 11/2 - 3 0.71154 7/2 + 4 1.00453 3/2 + * 5 1.01992 5/2 + 6 1.17970 5/2 + 7 1.30430 7/2 - 8 1.44620 5/2 + 9 1.46860 5/2 + 10 1.49680 5/2 + 11 1.51010 5/2 + 12 1.53000 3/2 + 13 1.57825 3/2 + 14 1.58800 11/2 - 15 1.58900 5/2 + 16 1.59310 15/2 - 17 1.62540 13/2 - ------------------- *) Coupled levels in CC calculation Table 2. Level density parameters -------------------------------------------------------- Nuclide a* Pair Eshell T E0 Ematch 1/MeV MeV MeV MeV MeV MeV -------------------------------------------------------- Sn-118 14.7649 2.2094 1.1802 0.6386 0.7048 6.4391 Sn-117 15.0000 1.1094 1.4418 0.5905 -0.0864 4.7453 Sn-116 14.5525 2.2283 1.0766 0.6163 1.0296 5.9849 Sn-115 14.7000 1.1190 1.0063 0.5584 0.3775 4.0538 In-117 14.0356 1.1094 2.5136 0.6228 -0.3934 5.1460 In-116 14.8000 0.0000 2.5937 0.5594 -1.1570 3.3948 In-115 13.8308 1.1190 2.4621 0.6294 -0.3710 5.1585 In-114 13.8000 0.0000 2.2509 0.5975 -1.1306 3.4976 Cd-116 14.5525 2.2283 2.7100 0.6353 0.3516 6.7335 Cd-115 16.4000 1.1190 3.1141 0.5877 -0.9615 5.6632 Cd-114 15.2000 2.2478 2.7414 0.6005 0.5136 6.4627 Cd-113 15.9000 1.1289 2.9350 0.6265 -1.2162 6.1086 Cd-112 15.1000 2.2678 2.4135 0.6741 -0.1957 7.5999 -------------------------------------------------------- Table 3. Gamma-ray strength function for Sn-118 -------------------------------------------------------- * E1: ER = 15.44 (MeV) EG = 4.86 (MeV) SIG = 279.00 (mb) ER = 6.20 (MeV) EG = 1.90 (MeV) SIG = 2.90 (mb) * M1: ER = 8.36 (MeV) EG = 4.00 (MeV) SIG = 1.40 (mb) * E2: ER = 12.84 (MeV) EG = 4.69 (MeV) SIG = 2.69 (mb) -------------------------------------------------------- References 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 2) Alfimenkov, V.P. et al.: Nucl. Phys., A398, 93 (1983). 3) Bollinger, L.M., Thomas, G.E.: Phys. Rev., 171,1293(1968). 4) Smith, D.A. et al.: Phys. Rev., C59, 2836 (1999). 5) Georgiev, G.P. et al.: YK-1996, p.64 (1996). 6) Mughabghab, S.F.: "Atlas of Neutron Resonances", Elsevier (2006). 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) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 12) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 13) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962). 14) Kalbach,C.: Phys. Rev. C33, 818 (1986). 15) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 16) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 17) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 18) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 19) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 20) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).