50-Sn-124

 50-Sn-124 JAEA       EVAL-Dec09 N.Iwamoto,K.Shibata              
                      DIST-MAY10                       20100119   
----JENDL-4.0         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.                                  
                                                                  
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.                                                        
                                                                  
    Unresolved resonance region : 80 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           4.4806e+00                                 
       Elastic         4.3449e+00                                 
       n,gamma         1.3568e-01           7.8618e+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 /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= 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= 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: 0,1,16 (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-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) 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).