50-Sn-119

 50-Sn-119 JAEA       EVAL-Dec09 N.Iwamoto,K.Shibata              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 5046                               
-----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.                                  
                                                                  
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 1.3 keV      
      In JENDL-3.3, resonance parameters were based on Mughabghab 
      et al./1/ 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/2/.  Average radiation       
      width of 90 meV and scattering radius of 6.0 fm were 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 values of J and L were reassigned on the    
      basis of the work done by Georgiev et al./3/  Radiation     
      widths of some levels were taken from the same literature   
      /3/.                                                        
                                                                  
    Unresolved resonance region : 1.3 keV - 200 keV               
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /4/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /5/ and CCONE /6/. 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           6.8704e+00                                 
       Elastic         4.6943e+00                                 
       n,gamma         2.1761e+00           5.5770e+00            
       n,alpha         8.5362e-11                                 
      ----------------------------------------------------------  
         (*) 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 /6/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /6/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /6/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /6/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /6/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /6/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /6/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /6/              
***************************************************************** 
                                                                  
  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./7/ (+)                      
      proton   omp: Kunieda,S. et al./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: Huizenga,J.R. and Igo,G./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 Sn-119                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  1/2 +  *                                           
   1  0.02387  3/2 +                                              
   2  0.08953 11/2 -                                              
   3  0.78701  7/2 +                                              
   4  0.92051  3/2 +  *                                           
   5  0.92139  5/2 +                                              
   6  1.06000  5/2 +                                              
   7  1.06240  7/2 -                                              
   8  1.08944  5/2 +                                              
   9  1.18773  5/2 +                                              
  10  1.21000 11/2 -                                              
  11  1.24971  1/2 +                                              
  12  1.30440 13/2 -                                              
  13  1.30930 15/2 -                                              
  14  1.35480  5/2 +                                              
  15  1.37880 13/2 -                                              
  16  1.39000 11/2 -                                              
  17  1.51000  3/2 -                                              
  18  1.55440  5/2 +                                              
  19  1.56200  3/2 +                                              
  20  1.57180  1/2 +                                              
  21  1.59000  5/2 +                                              
  22  1.61710  5/2 -                                              
  23  1.63300  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         
  --------------------------------------------------------        
   Sn-120 14.7000  2.1909  0.8820  0.6695  0.4967  6.8161         
   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         
   In-119 14.2400  1.1000  2.1477  0.6266 -0.3980  5.1833         
   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         
   Cd-118 14.7649  2.2094  2.3367  0.6412  0.3136  6.8030         
   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         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Sn-120                   
  --------------------------------------------------------        
  * E1: ER = 15.37 (MeV) EG = 5.10 (MeV) SIG = 285.00 (mb)        
        ER =  6.20 (MeV) EG = 1.30 (MeV) SIG =   4.60 (mb)        
  * M1: ER =  8.31 (MeV) EG = 4.00 (MeV) SIG =   1.59 (mb)        
  * E2: ER = 12.77 (MeV) EG = 4.67 (MeV) SIG =   2.66 (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) Georgiev, G.P. et al.: 94 Gatlinburg, p.299 (1994).           
 4) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 5) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 6) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 7) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 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) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
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).