50-Sn-126

 50-Sn-126 JAEA       EVAL-Dec09 N.Iwamoto                        
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 5067                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
09-12 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 resonances                       
    No resolved resonance parameters                              
                                                                  
    Unresolved resonance region : 6.8 keV - 200 keV               
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /1/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /2/ and CCONE /3/. 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           4.9138e+00                                 
       Elastic         4.8197e+00                                 
       n,gamma         9.0035e-02           9.6380e-02            
      ----------------------------------------------------------  
         (*) 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 /3/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /3/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /3/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /3/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /3/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /3/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /3/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /3/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /3/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1 (see Table 1)                           
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./4/ (+)                      
      proton   omp: Kunieda,S. et al./4/                          
      deuteron omp: Lohr,J.M. and Haeberli,W./5/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./6/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./6/      
      alpha    omp: Huizenga,J.R. and Igo,G./7/                   
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/8/                               
    * Global parametrization of Koning-Duijvestijn/9/             
      was used.                                                   
    * Gamma emission channel/10/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/11/ 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/12/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /13/,/14/ 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-126                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  1.14115   2  +  *                                           
   2  2.04974   4  +                                              
   3  2.11079   2  +                                              
   4  2.13009   2  +                                              
   5  2.16154   5  -                                              
   6  2.19422   4  -                                              
   7  2.21899   7  -                                              
   8  2.25652   3  -                                              
   9  2.27685   2  +                                              
  10  2.29800   1  +                                              
  11  2.37046   2  +                                              
  12  2.47193   4  +                                              
  13  2.47751   6  -                                              
  14  2.48824   8  +                                              
  15  2.55000   3  -                                              
  16  2.56450  10  +                                              
  17  2.63103   3  +                                              
  18  2.63664   2  +                                              
  19  2.66298   7  +                                              
  20  2.71206   4  +                                              
  21  2.72000   3  -                                              
  22  2.74257   1  -                                              
  -------------------                                             
  *) 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-127 16.3728  1.0648 -3.3108  0.7888 -0.7788  7.5329         
   Sn-126 15.6101  2.1381 -2.6047  0.8273 -0.2048  9.2786         
   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         
   In-126 15.5298  0.0000 -2.3056  0.6831 -0.9476  4.1443         
   In-125 14.8507  1.0733 -1.3884  0.6557  0.2272  4.7782         
   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         
   Cd-124 15.3994  2.1553 -0.6710  0.6750  0.7153  6.7076         
   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         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Sn-127                   
  --------------------------------------------------------        
  * E1: ER = 15.39 (MeV) EG = 4.82 (MeV) SIG = 288.56 (mb)        
  * M1: ER =  8.16 (MeV) EG = 4.00 (MeV) SIG =   0.65 (mb)        
  * E2: ER = 12.53 (MeV) EG = 4.59 (MeV) SIG =   2.56 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 2) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 3) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 4) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 5) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 6) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
 7) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
 8) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
 9) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
10) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
11) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
12) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
13) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
14) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).