79-Au-197

 79-Au-197 JAEA       EVAL-Feb10 N.Iwamoto                        
                      DIST-AUG13                       20130813   
----JENDL-4.0u1       MATERIAL 7925                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
History                                                           
10-02 The resolved resonance parameters were evaluated by         
      N.Iwamoto.                                                  
      The data above the resolved resonance region were evaluated 
      and compiled by N.Iwamoto.                                  
13-08 The primary gamma data in MF6/MT102 were included in        
      continuum spectra. The maximum energies of continuum        
      spectrum in MF6/MT16,22,28,32,33,91,102 were revised.       
                                                                  
MF= 1 General information                                         
  MT=451 Descriptive data and directory                           
                                                                  
MF= 2  Resonance parameters                                       
  MT=151 Resolved and unresolved resonance parameters             
    Resolved resonance region : below 2.3 keV                     
      Resolved resonance parameters were taken from Mughabghab    
      /1/, supplimented by the data of Desjardins et al. /2/      
      and Alves et al. /3/. If the total spin J of resonance      
      level was not known, it was determined from the spin        
      distribution of the level density randomly. The negative    
      resonance was placed so as to reproduce the cross sections  
      at thermal energy recommended by Mughabghab /1/.            
                                                                  
      Thermal cross sections and resonance integrals at 300 K     
      ----------------------------------------------------------  
                       0.0253 eV           res. integ. (*)        
                        (barn)               (barn)               
      ----------------------------------------------------------  
       Total           1.0657e+02                                 
       Elastic         7.9220e+00                                 
       n,gamma         9.8649e+01           1.5711e+03            
       n,alpha         7.4569e-09                                 
      ----------------------------------------------------------  
         (*) 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= 24 (n,2na) cross section                                    
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 32 (n,nd) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 33 (n,nt) cross section                                     
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 41 (n,2np) 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= 24 (n,2na) reaction                                         
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 28 (n,np) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 32 (n,nd) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 33 (n,nt) reaction                                          
    Calculated with CCONE code /4/.                               
                                                                  
  MT= 41 (n,2np) 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: 0,3,6 (see Table 1)                         
                                                                  
    * optical model potential                                     
      neutron  omp: Koning,A.J. and Delaroche,J.P./5/             
      proton   omp: Koning,A.J. and Delaroche,J.P./6/             
      deuteron omp: Lohr,J.M. and Haeberli,W./7/                  
      triton   omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      He3      omp: Becchetti Jr.,F.D. and Greenlees,G.W./8/      
      alpha    omp: Huizenga,J.R. and Igo,G./9/                   
                                                                  
  2) Two-component exciton model/10/                              
    * Global parametrization of Koning-Duijvestijn/11/            
      was used.                                                   
    * Gamma emission channel/12/ was added to simulate direct     
      and semi-direct capture reaction.                           
                                                                  
  3) Hauser-Feshbach statistical model                            
    * Width fluctuation correction/13/ 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/14/.           
      Parameters are shown in Table 2.                            
    * Gamma-ray strength function of generalized Lorentzian form  
      /15/,/16/ 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 Au-197                                   
  -------------------                                             
  No.  Ex(MeV)  J  PI                                             
  -------------------                                             
   0  0.00000  3/2 +  *                                           
   1  0.07735  1/2 +                                              
   2  0.26879  3/2 +                                              
   3  0.27899  5/2 +  *                                           
   4  0.40915 11/2 -                                              
   5  0.50250  5/2 +                                              
   6  0.54750  7/2 +  *                                           
   7  0.58300  1/2 +                                              
   8  0.73670  7/2 +                                              
   9  0.85550  9/2 +                                              
  10  0.88200  5/2 +                                              
  11  0.88811  1/2 +                                              
  12  0.93600  5/2 +                                              
  13  0.94800  5/2 -                                              
  14  1.04510  5/2 +                                              
  15  1.12000 11/2 +                                              
  16  1.15050  5/2 +                                              
  17  1.21730  3/2 +                                              
  18  1.22000 11/2 -                                              
  19  1.23100 11/2 +                                              
  20  1.24200  1/2 +                                              
  21  1.26300  7/2 +                                              
  -------------------                                             
  *) Coupled levels in CC calculation                             
                                                                  
Table 2. Level density parameters                                 
  --------------------------------------------------------        
  Nuclide      a*    Pair  Eshell       T      E0  Ematch         
            1/MeV     MeV     MeV     MeV     MeV     MeV         
  --------------------------------------------------------        
   Au-198 23.5000  0.0000 -3.4225  0.5829 -1.6170  4.9907         
   Au-197 22.0000  0.8550 -2.6591  0.5684 -0.5329  5.2839         
   Au-196 23.9000  0.0000 -2.0588  0.5154 -1.3667  4.0713         
   Au-195 21.7732  0.8593 -1.4759  0.5524 -0.6845  5.2681         
   Pt-197 23.5000  0.8550 -2.4961  0.5878 -1.1873  6.3005         
   Pt-196 23.9000  1.7143 -2.1512  0.5435  0.0374  6.3674         
   Pt-195 22.4000  0.8593 -1.4563  0.5983 -1.4448  6.5066         
   Pt-194 22.5803  1.7231 -1.1591  0.5393  0.0580  6.1996         
   Ir-196 22.6017  0.0000 -1.8165  0.3966 -0.2033  1.7963         
   Ir-195 21.7732  0.8593 -1.2540  0.5660 -0.9225  5.6240         
   Ir-194 23.4000  0.0000 -1.0076  0.5222 -1.6745  4.3969         
   Ir-193 23.3000  0.8638 -0.5016  0.5194 -0.9094  5.3195         
   Ir-192 23.8000  0.0000 -0.0310  0.4621 -1.2968  3.5533         
   Ir-191 21.3859  0.8683  0.2942  0.5392 -0.9709  5.4012         
  --------------------------------------------------------        
                                                                  
Table 3. Gamma-ray strength function for Au-198                   
  --------------------------------------------------------        
  * E1: ER = 13.73 (MeV) EG = 4.76 (MeV) SIG = 502.00 (mb)        
        ER =  5.50 (MeV) EG = 1.50 (MeV) SIG =   5.50 (mb)        
        ER =  1.70 (MeV) EG = 0.50 (MeV) SIG =   0.04 (mb)        
  * M1: ER =  7.03 (MeV) EG = 4.00 (MeV) SIG =   1.47 (mb)        
  * E2: ER = 10.81 (MeV) EG = 3.73 (MeV) SIG =   5.03 (mb)        
  --------------------------------------------------------        
                                                                  
References                                                        
 1) Mughabghab,S.F.: "Atlas of Neutron Resonances, Fifth          
    Edition: Resonance Parameters and Thermal Cross Sections.     
    Z=1-100", Elsevier Science (2006).                            
 2) Desjardins,J.S. et al.: Phys. Rev., 120, 2214 (1960).         
 3) Alves,R.N. et al.: Nucl. Phys., A131, 450 (1969).             
 4) Iwamoto,O.: J. Nucl. Sci. Technol., 44, 687 (2007).           
 5) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 6) Koning,A.J. and Delaroche,J.P.: Nucl. Phys. A713, 231 (2003)  
    [Global potential].                                           
 7) Lohr,J.M. and Haeberli,W.: Nucl. Phys. A232, 381 (1974).      
 8) Becchetti Jr.,F.D. and Greenlees,G.W.: Ann. Rept.             
    J.H.Williams Lab., Univ. Minnesota (1969).                    
 9) Huizenga,J.R. and Igo,G.: Nucl. Phys. 29, 462 (1962).         
10) Kalbach,C.: Phys. Rev. C33, 818 (1986).                       
11) Koning,A.J., Duijvestijn,M.C.: Nucl. Phys. A744, 15 (2004).   
12) Akkermans,J.M., Gruppelaar,H.: Phys. Lett. 157B, 95 (1985).   
13) Moldauer,P.A.: Nucl. Phys. A344, 185 (1980).                  
14) Mengoni,A. and Nakajima,Y.: J. Nucl. Sci. Technol., 31, 151   
    (1994).                                                       
15) Kopecky,J., Uhl,M.: Phys. Rev. C41, 1941 (1990).              
16) Kopecky,J., Uhl,M., Chrien,R.E.: Phys. Rev. C47, 312 (1990).