80-Hg-196

 80-Hg-196 JNDC       EVAL-SEP97 K.SHIBATA, T.FUKAHORI, S.CHIBA,+ 
 JNST 34, 1171 (1997) DIST-JUL13                       20130520   
----JENDL-4.0u1       MATERIAL 8025                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
 97-09  Evaluation was performed for JENDL-3.3.                   
 97-10  Compiled by T.Fukahori (jaeri).                           
 99-04  Comments were added by T.Fukahori                         
 01-07  Modified by K.Shibata for JENDL-3.3.                      
        (3,251)   deleted.                                        
        (4,2)     transformation matrix deleted.                  
        (5,16-91) INT=22.                                         
 10-01  Modified by K.Shibata for JENDL-4.0.                      
        (1,451)   Updated.                                        
        (2,151)   Unresolved parameters added.                    
        (3,1)     Re-calculated from partial cross sections.      
        (3,4)     Re-calculated from partial cross sections.      
 13-05  Modified by K.Shibata for JENDL-4.0u1                     
        (5,16)    Spectrum at 10 MeV was revised to avoid negative
                  Kerma factors.                                  
        (5,17)    Spectra at 16 and 18 MeV was revised to avoid   
                  negative Kerma factors.                         
                                                                  
 mf=1  General information                                        
   mt=451  Descriptive data and dictionary                        
                                                                  
 mf=2  Resonance parameters                                       
   mt=151 Resolved resonances                                     
       Resonance region = 1.0e-5 eV to 102.85 eV                  
       Parameters for the multilevel Breit-Wigner formula         
       were adopted from the compilation by Mughabghab+ /1/.      
       R=9.5 fm was selected to reproduce the thermal elastic     
       scattering cross section of natural Mercury measured by    
       Hibdon+ /2/.                                               
                                                                  
       ***********************************************************
       For JENDL-4.0, the unresolved resonance parameters were    
       obtained so as to reproduce the total and capture cross    
       sections in the energy region from 102.85 eV to 100 keV.   
       The parameters should be used only for self-shielding      
       calculations.                                              
       ***********************************************************
                                                                  
       calculated 2200-m/s cross sections and res. integrals.     
                       2200-m/s     res. integ.                   
          elastic        110 b         -                          
          capture       3078 b        419 b                       
          total         3188 b                                    
                                                                  
 mf=3  Neutron cross sections                                     
   mt=1    Total                                                  
       Below 102.85 eV , no background cross section was given.   
       spherical optical model calculation was made by            
       casthy code /3/ above 102.85 eV.  Modified Walter-Guss     
       potential parameters /4,5/ were used.                      
                                                                  
   mt=2    Elastic scattering                                     
       Given as total minus nonelastic cross sections.            
                                                                  
   mt=16,17,22,28,103,104,107                                     
       (n,2n),(n,3n),(n,n'a),(n,n'p),(n,p),(n,d),(n,a)            
       Calculated by scincros-ii /4/ with the following           
       parameters.                                                
                                                                  
         optical potential parameters                             
           neutron : modified Walter-Guss /4,5/                   
           proton  : combined Perey /6/ and Walter-Guss           
           alpha   : Lemos /7/ modified by Arthur-Young /8/       
           deuteron: Lohr-Haeberli /9/                            
                                                                  
         level density parameters                                 
            nuclei  a(1/MeV)  pair(MeV)  t(MeV)  Ex(MeV)  Ec(MeV) 
            Hg-194    21.5      2.00      0.42    3.66     2.89   
            Hg-195    21.0      0.87      0.59    5.45     0.89   
            Hg-196    20.5      1.71      0.49    4.36     2.50   
            Hg-197    20.0      0.87      0.63    6.00     1.03   
            Hg-198    19.5      1.66      0.63    6.45     1.91   
            Hg-199    18.0      0.87      0.70    6.48     0.75   
            Hg-200    17.0      1.69      0.75    7.81     2.19   
            Hg-201    16.0      0.87      0.79    7.22     0.77   
            Hg-202    15.0      1.58      0.84    8.35     1.79   
            Hg-203    14.5      0.87      0.83    7.02     0.58   
            Hg-204    14.0      1.28      0.82    6.88     2.81   
            Hg-205    13.5      0.87      0.84    6.59     1.86   
            Au-195    21.0      0.84      0.57    5.05     1.11   
            Au-196    20.5      0.00      0.43    1.63     0.60   
            Au-197    19.6      0.79      0.58    4.70     1.26   
            Au-198    19.1      0.00      0.62    4.52     0.57   
            Au-199    18.0      0.82      0.65    5.52     1.16   
            Au-200    17.0      0.00      0.64    4.07     0.47   
            Au-201    15.5      0.71      0.73    5.53     0.90   
            Au-202    15.0      0.00      0.77    5.40     0.00   
            Au-203    14.0      0.41      0.82    6.01     0.00   
            Au-204    13.0      0.00      0.87    5.84     0.00   
            Pt-192    23.2      1.84      0.58    7.15     1.44   
            Pt-193    22.5      0.71      0.58    5.64     0.52   
            Pt-194    21.0      1.55      0.59    6.28     1.67   
            Pt-195    21.0      0.71      0.61    5.69     0.66   
            Pt-196    20.0      1.50      0.58    5.63     1.97   
            Pt-197    18.9      0.71      0.67    6.11     0.60   
            Pt-198    18.7      1.53      0.65    6.53     1.52   
            Pt-199    18.5      0.71      0.67    6.09     0.51   
            Pt-200    18.0      1.42      0.66    6.29     0.00   
            Pt-201    17.5      0.71      0.68    5.66     0.00   
                                                                  
   mt=4,51-70,91  Inelastic scattering                            
       The casthy and sincros-ii calculations were adopted. The   
       direct-process component was considered by the DWBA theory.
       Deformation parameters were taken from ref. /10/ and       
       listed in the table below for adopted levels.              
                                                                  
       The level scheme is given as follows:                      
          no.     energy(MeV)  spin-parity  deformation-parameter 
          g.s.      0.0          0 +                              
           1.       0.4260       2 +          L=2, beta=0.116     
           2.       1.0362       2 +                              
           3.       1.0609       4 +                              
           4.       1.3189       0 +                              
           5.       1.3906       2 +                              
           6.       1.7568       5 -                              
           7.       1.7753       2 +                              
           8.       1.7850       6 +                              
           9.       1.8147       2 +                              
          10.       1.8408       7 -                              
          11.       1.8450       1 +                              
          12.       1.9215       2 +                              
          13.       1.9787       1 +                              
          14.       2.0123       1 +                              
          15.       2.0637       9 -                              
          16.       2.2626       8 +                              
          17.       2.3460       5 -                              
          18.       2.3596      10 +                              
          19.       2.4552       1 +                              
          20.       2.4955       2 +                              
       Continuum levels were assumed above 2.496 MeV.             
                                                                  
   mt=102  Capture                                                
       Below 102.85 ev, no background cross section was given.    
       The casthy calculation was adopted above 102.85 eV.        
                                                                  
 mf=4  Angular distributions of secondary neutrons                
   mt=2,51-70                                                     
       Optical and statistical-model calculations were adopted.   
       The DWBA calculations were added.                          
   mt=16,17,22,28,91                                              
       Calculated with sincros-ii.                                
                                                                  
 mf=5  Energy spectrum of secondary neutron                       
   mt=16,17,22,28,91                                              
       Calculated with sincros-ii.                                
                                                                  
 mf=12 Photon multiplicities and transition probability arrays    
   mt=16,17,22,28,51-70,91,102,103,104,107                        
       Multiplicities were calculated with casthy and sincros-ii. 
                                                                  
 mf=14 Photon angular distributions                               
   mt=16,17,22,28,51-70,91,102,103,104,107                        
       Assumed to be isotropic.                                   
                                                                  
 mf=15 Photon energy spectra                                      
   mt=16,17,22,28,91,102,103,104,107                              
       Calculated with casthy and sincros-ii.                     
                                                                  
 References                                                       
  1) Mughabghab S.F. et al.: "Neutron Cross Sections", Vol.1,     
     Part B, Academic Press (1984).                               
  2) Hibdon C.T. et al.: Phys. Rev., 82, 560 (1951).              
  3) Igarasi S. and Fukahori T.: JAERI-1321 (1991).               
  4) Yamamuro N.: JAERI-M 90-006 (1990).                          
  5) Walter R.L. and Guss P.P.: Proc. Int. Conf. on Nucl. Data    
     for Basic and Applied Sci., Santa Fe, May 13-17, 1985,       
     p.1079 (1986).                                               
  6) Perey F.G.: Phys. Rev., 131, 745 (1963).                     
  7) Lemos O.F.: Orsay Rep., Ser. A. No. 136 (1972).              
  8) Arthur E.D. and Young P.G.: LA-8626-MS (1980).               
  9) Lohr J.M. and Haeberli W.: Nucl. Phys., A232, 381 (1974).    
 10) Raman S. et al: At. Data Nucl. Data Tables, 36, 1 (1987).