50-Sn-118 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata DIST-DEC21 20100119 ----JENDL-5 MATERIAL 5043 -----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. 21-10 JENDL-5b3 revised by N.Iwamoto (MF2/MT151) revised (MF3,6/MT600-849) added (MF8/MT4-107) added (MF9/MT102,107) added (MF10/MT16,28,103,104,105) added (MF3/MT1,2,4,103-107) recalculated 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 15.0 keV In JENDL-3.3, resonance parameters and scattering radius were based on Mughabghab et al./1/. The levels whose neutron width was unknown were assumed to be p-wave resonances, and a reduced neutron width of 250 meV was tentatively given for these levels. Neutron orbital angular momentum L of some resonances was estimated with a method of Bollinger and Thomas/2/. Average radiation width was assumed to be 85 meV according to the systematics from the 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 parameters were replaced with the ones obtained by Wisshak et al./3/ in the region from 2.9 to 20 k The values of unknown L were estimated by considering the magnitude of g*Gamma_n. The J values were estimated by a random number method. In JENDL-5 the 289-eV p-wave resonances were deleted, based on the results of Kimura et al./4/. Unresolved resonance region : 15.0 keV - 200 keV The unresolved resonance paramters (URP) were determined by ASREP code /5/ so as to reproduce the evaluated total and capture cross sections calculated with optical model code OPTMAN /6/ and CCONE /7/. 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 4.44530E+00 Elastic 4.22975E+00 n,gamma 2.15555E-01 5.10142E+00 n,alpha 9.71960E-26 7.70681E-25 ---------------------------------------------------------- (*) 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 /7/. MT= 16 (n,2n) cross section Calculated with CCONE code /7/. MT= 17 (n,3n) cross section Calculated with CCONE code /7/. MT= 22 (n,na) cross section Calculated with CCONE code /7/. MT= 28 (n,np) cross section Calculated with CCONE code /7/. MT= 51-91 (n,n') cross section Calculated with CCONE code /7/. MT=102 Capture cross section Calculated with CCONE code /7/. MT=103, 600-649 (n,p) cross section Calculated with CCONE code /7/. MT=104, 650-699 (n,d) cross section Calculated with CCONE code /7/. MT=105, 700-749 (n,t) cross section Calculated with CCONE code /7/. MT=106, 750-799 (n,He3) cross section Calculated with CCONE code /7/. MT=107, 800-849 (n,a) cross section Calculated with CCONE code /7/. MF= 4 Angular distributions of emitted neutrons MT= 2 Elastic scattering Calculated with CCONE code /7/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /7/. MT= 17 (n,3n) reaction Calculated with CCONE code /7/. MT= 22 (n,na) reaction Calculated with CCONE code /7/. MT= 28 (n,np) reaction Calculated with CCONE code /7/. MT= 51-91 (n,n') reaction Calculated with CCONE code /7/. MT=102 Capture reaction Calculated with CCONE code /7/. MT=600-649 (n,p) reaction Calculated with CCONE code /7/. MT=650-699 (n,d) reaction Calculated with CCONE code /7/. MT=700-749 (n,t) reaction Calculated with CCONE code /7/. MT=750-799 (n,He3) reaction Calculated with CCONE code /7/. MT=800-849 (n,a) reaction Calculated with CCONE code /7/. MF= 8 Information on decay data MT= 4 (n,n') reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /7/. MT=107 Capture reaction Calculated with CCONE code /7/. MF=10 Nuclide production reactions MT= 16 (n,2n) reaction Calculated with CCONE code /7/. MT= 28 (n,np) reaction Calculated with CCONE code /7/. MT=103 (n,p) reaction Calculated with CCONE code /7/. MT=104 (n,d) reaction Calculated with CCONE code /7/. MT=105 (n,t) reaction Calculated with CCONE code /7/. ***************************************************************** Nuclear Model Calculation with CCONE code /7/ ***************************************************************** Models and parameters used in the CCONE calculation 1) Optical model * coupled channels calculation coupled levels: 0,1,8 (see Table 1) * optical model potential neutron omp: Kunieda,S. et al./8/ (+) proton omp: Kunieda,S. et al./8/ deuteron omp: Lohr,J.M. and Haeberli,W./9/ triton omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/ He3 omp: Becchetti Jr.,F.D. and Greenlees,G.W./10/ alpha omp: Huizenga,J.R. and Igo,G./11/ (+) omp parameters were modified. 2) Two-component exciton model/12/ * Global parametrization of Koning-Duijvestijn/13/ was used. * Gamma emission channel/14/ was added to simulate direct and semi-direct capture reaction. 3) Hauser-Feshbach statistical model * Width fluctuation correction/15/ 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/16/. Parameters are shown in Table 2. * Gamma-ray strength function of generalized Lorentzian form /17/,/18/ 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-118 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 0 + * 1 1.22967 2 + * 2 1.75831 0 + 3 2.04288 2 + 4 2.05691 0 + 5 2.12000 2 + 6 2.28034 4 + 7 2.32123 5 - 8 2.32485 3 - * 9 2.32802 2 + 10 2.40322 2 + 11 2.40800 4 + 12 2.48887 4 + 13 2.49688 0 + 14 2.53000 5 - 15 2.57491 7 - 16 2.57700 2 + 17 2.67735 2 + 18 2.72500 2 + 19 2.73379 4 + 20 2.73801 1 + 21 2.77394 4 - 22 2.81700 6 - 23 2.81717 3 - 24 2.87870 5 - 25 2.88900 8 + 26 2.90387 2 + 27 2.92972 1 + 28 2.93400 2 + 29 2.96344 4 + 30 2.97200 4 + 31 2.99100 3 + 32 2.99945 6 + 33 3.01521 2 - 34 3.02000 0 + 35 3.04835 4 - 36 3.05216 7 + 37 3.05722 2 + 38 3.08921 0 + 39 3.10806 0 + 40 3.13748 0 + ------------------- *) 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-119 15.8000 1.1000 1.4670 0.5796 -0.2200 4.8655 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 In-118 14.6950 0.0000 2.5427 0.5650 -1.1604 3.4261 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 Cd-117 16.7000 1.1094 2.9235 0.6001 -1.1587 5.9328 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 -------------------------------------------------------- Table 3. Gamma-ray strength function for Sn-119 -------------------------------------------------------- * E1: ER = 15.53 (MeV) EG = 4.81 (MeV) SIG = 253.00 (mb) ER = 6.40 (MeV) EG = 1.80 (MeV) SIG = 1.50 (mb) * M1: ER = 8.34 (MeV) EG = 4.00 (MeV) SIG = 1.00 (mb) * E2: ER = 12.81 (MeV) EG = 4.68 (MeV) SIG = 2.67 (mb) -------------------------------------------------------- References 1) Mughabghab, S.F. et al.: "Neutron Cross Sections, Vol. I, Part A", Academic Press (1981). 2) Bollinger, L.M., Thomas, G.E.: Phys. Rev., 171,1293(1968). 3) Wisshak,K et al.: Phys. Rev., C54, 2732 (1996). 4) Kimura,A. et al.: Nucl. Data Sheets, 119, 150 (2014). 5) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999) [in Japanese]. 6) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004). 7) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007). 8) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007). 9) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974). 10) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept. J.H.Williams Lab., Univ. Minnesota (1969). 11) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962). 12) Kalbach,C.: Phys. Rev. C33, 818 (1986). 13) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004). 14) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985). 15) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980). 16) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151 (1994). 17) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990). 18) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).