50-Sn-124 JAEA EVAL-Dec09 N.Iwamoto,K.Shibata DIST-DEC21 20100119 ----JENDL-5 MATERIAL 5061 -----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) added (MF10/MT16,28,103,104,105,107) 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 80 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 830 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/. Averaged radiation width of 140 meV was derived from the systematics of measured values for neighboring nuclides. A negative resonance was added so as to reproduce the thermal capture and elastic scattering cross sections given by Mughabghab et al. In JENDL-4, the data above 14 keV were taken from the wrok of Carlton et al./3/. A value of 140 meV was assumed for the radiation width. The upper boudary was extended to 80 keV. In JENDL-5 the 579- and 950-eV p-wave resonances were deleted, based on the results of Kimura et al./4/. Unresolved resonance region : 80 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 4.48059E+00 Elastic 4.34491E+00 n,gamma 1.35684E-01 7.71993E+00 ---------------------------------------------------------- (*) 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/. 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/. MT=107 (n,a) 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: 0,1,16 (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-124 ------------------- No. Ex(MeV) J PI ------------------- 0 0.00000 0 + * 1 1.13174 2 + * 2 2.10171 4 + 3 2.10900 5 - 4 2.12930 0 + 5 2.12960 2 + 6 2.19216 4 - 7 2.20462 5 - 8 2.22176 4 + 9 2.32501 7 - 10 2.36650 4 - 11 2.42632 2 + 12 2.44800 8 + 13 2.45434 6 + 14 2.56815 6 - 15 2.57844 8 + 16 2.60250 3 - * 17 2.61445 4 - 18 2.65660 10 + 19 2.68852 0 + 20 2.70178 5 - 21 2.70319 2 + 22 2.70600 4 + 23 2.75305 4 - 24 2.83658 3 + 25 2.85513 6 - 26 2.87537 2 + 27 2.87867 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-125 16.1653 1.0733 -1.4420 0.6783 -0.3617 5.7801 Sn-124 15.3994 2.1553 -1.0033 0.7260 0.3147 7.5454 Sn-123 15.9572 1.0820 -0.0224 0.6542 -0.5670 5.7354 Sn-122 15.1883 2.1729 0.1587 0.6646 0.6099 6.7179 In-124 15.3217 0.0000 -0.3915 0.6954 -1.7265 4.9806 In-123 14.6475 1.0820 0.1996 0.6115 0.1625 4.5397 In-122 15.1132 0.0000 0.9721 0.6133 -1.2958 3.9041 In-121 14.4439 1.0909 1.3854 0.6275 -0.2553 5.0642 Cd-123 15.9572 1.0820 0.4830 0.7005 -1.2943 6.7635 Cd-122 15.1883 2.1729 0.5773 0.6134 0.9712 5.9920 Cd-121 15.7486 1.0909 1.5385 0.6783 -1.3360 6.5598 Cd-120 14.9768 2.1909 1.6826 0.6507 0.3296 6.8575 Cd-119 15.5394 1.1000 2.5578 0.6443 -1.1874 6.1408 -------------------------------------------------------- Table 3. Gamma-ray strength function for Sn-125 -------------------------------------------------------- * E1: ER = 15.45 (MeV) EG = 4.85 (MeV) SIG = 283.55 (mb) * M1: ER = 8.20 (MeV) EG = 4.00 (MeV) SIG = 0.65 (mb) * E2: ER = 12.60 (MeV) EG = 4.61 (MeV) SIG = 2.58 (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) Carlton, R.F.: Phys. Rev., C54, 2445 (1996). 4) Kimura et al.: EPJ Web of Conferences, 146, 11031 (2017). 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).