50-Sn-116

 50-Sn-116 JAEA       EVAL-Dec09 N.Iwamoto,K.Shibata              
                      DIST-MAY10                       20100119   
----JENDL-4.0         MATERIAL 5037                               
-----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 32.8 keV      
      The parameters are based on the work of Koehler et al./1/   
      A value of 6.32 fm was used for R.                          
                                                                  
    Unresolved resonance region : 32.8 keV - 200 keV              
      The unresolved resonance paramters (URP) were determined by 
      ASREP code /2/ so as to reproduce the evaluated total and   
      capture cross sections calculated with optical model code   
      OPTMAN /3/ and CCONE /4/. 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           4.6469e+00                                 
       Elastic         4.5218e+00                                 
       n,gamma         1.2515e-01           1.2175e+01            
       n,alpha         2.1168e-16                                 
      ----------------------------------------------------------  
         (*) 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 /4/.                               
                                                                  
  MT= 16 (n,2n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') cross section                                  
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=103 (n,p) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=104 (n,d) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=105 (n,t) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
  MT=106 (n,He3) cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT=107 (n,a) cross section                                      
    Calculated with CCONE code /4/.                               
                                                                  
MF= 4 Angular distributions of emitted neutrons                   
  MT=  2 Elastic scattering                                       
    Calculated with CCONE code /4/.                               
                                                                  
MF= 6 Energy-angle distributions of emitted particles             
  MT= 16 (n,2n) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 17 (n,3n) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 22 (n,na) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 51-91 (n,n') reaction                                       
    Calculated with CCONE code /4/.                               
                                                                  
  MT=102 Capture reaction                                         
    Calculated with CCONE code /4/.                               
                                                                  
                                                                  
                                                                  
***************************************************************** 
       Nuclear Model Calculation with CCONE code /4/              
***************************************************************** 
                                                                  
  Models and parameters used in the CCONE calculation             
  1) Optical model                                                
    * coupled channels calculation                                
      coupled levels: 0,1,6 (see Table 1)                         
                                                                  
    * optical model potential                                     
      neutron  omp: Kunieda,S. et al./5/ (+)                      
      proton   omp: Kunieda,S. et al./5/                          
      deuteron omp: Lohr,J.M. and Haeberli,W./6/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./7/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./7/      
      alpha    omp: Huizenga,J.R. and Igo,G./8/                   
      (+) omp parameters were modified.                           
                                                                  
  2) Two-component exciton model/9/                               
    * Global parametrization of Koning-Duijvestijn/10/            
      was used.                                                   
    * Gamma emission channel/11/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/12/ 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/13/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /14/,/15/ 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-116                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000   0  +  *                                           
   1  1.29356   2  +  *                                           
   2  1.75686   0  +                                              
   3  2.02748   0  +                                              
   4  2.11232   2  +                                              
   5  2.22538   2  +                                              
   6  2.26616   3  -  *                                           
   7  2.36598   5  -                                              
   8  2.39088   4  +                                              
   9  2.52920   4  +                                              
  10  2.54571   0  +                                              
  11  2.58556   1  +                                              
  12  2.65044   2  +                                              
  13  2.77333   6  -                                              
  14  2.79055   0  +                                              
  15  2.80128   4  +                                              
  16  2.84382   2  +                                              
  17  2.90885   7  -                                              
  18  2.96003   2  +                                              
  19  2.99627   3  +                                              
  20  3.01644   6  -                                              
  21  3.03270   6  +                                              
  22  3.04640   4  +                                              
  23  3.08863   2  +                                              
  24  3.09693   4  +                                              
  25  3.10518   5  -                                              
  26  3.15773   3  -                                              
  27  3.17968   3  +                                              
  28  3.18400   3  -                                              
  29  3.19432   0  +                                              
  30  3.21000   7  -                                              
  31  3.22745   2  +                                              
  32  3.22795   8  -                                              
  33  3.22806   2  +                                              
  34  3.23602   0  +                                              
  35  3.25767   4  -                                              
  36  3.27760   6  +                                              
  37  3.28899   1  -                                              
  38  3.30900   6  -                                              
  39  3.31499   3  +                                              
  40  3.33378   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-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         
   Sn-114 14.3397  2.2478  0.6810  0.6658  0.7718  6.5831         
   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         
   In-113 13.6257  1.1289  2.0526  0.6704 -0.5799  5.6037         
   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         
   Cd-111 15.6000  1.1390  2.3788  0.6387 -1.0720  6.0644         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Sn-117                   
  --------------------------------------------------------        
  * E1: ER = 15.64 (MeV) EG = 5.04 (MeV) SIG = 259.00 (mb)        
        ER =  6.40 (MeV) EG = 1.80 (MeV) SIG =   1.50 (mb)        
  * M1: ER =  8.38 (MeV) EG = 4.00 (MeV) SIG =   1.09 (mb)        
  * E2: ER = 12.88 (MeV) EG = 4.71 (MeV) SIG =   2.70 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1)  Koehler, P.E., et al.: Phys. Rev., C64, 065802 (2001).       
 2) Kikuchi,Y. et al.: JAERI-Data/Code 99-025 (1999)              
    [in Japanese].                                                
 3) Soukhovitski,E.Sh. et al.: JAERI-Data/Code 2005-002 (2004).   
 4) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 5) Kunieda,S. et al.: J. Nucl. Sci. Technol. 44, 838 (2007).     
 6) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 7) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
 8) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
 9) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
10) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
11) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
12) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
13) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
14) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
15) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).