68-Er-162

 68-ER-162 TIT        EVAL-SEP00 A.K.M. HARUN-AR-RASHID+          
                      DIST-MAR02                       20020207   
----JENDL-3.3         MATERIAL 6825                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
2000-09 Evaluation was performed by A.K.M.Harun-ar-Rashid (tit),  
        M.Igashira (tit), T.Ohsaki (tit), and K.Shibata (jaeri).  
2001-02 Compiled by K.Shibata (jaeri).                            
        evaluation was performed for jendl-3.3                    
                                                                  
 mf=1  General information                                        
   mt=451  Descriptive data and dictionary                        
                                                                  
 mf=2  Resonance parameters                                       
   mt=151 Resolved resonances                                     
     resonance range (1.0e-05 to 250.0 eV).                       
     Resolved resonance parameters from ref. 1 (Ehi=250.0 eV).    
     The bound level at -32.5 eV has Gamma-n = 0.11967 eV and     
     Gamma-gamma = 0.1 eV.  This choice gives the desired         
     value for the thermal capture cross section, 19+-2 b [2].    
     Values of Gamma-gamma not given in Ref.1 are set to 0.1 eV.  
     The value for the scattering radius is 8.1fm.   Highest      
     energy resonance included is 250.0 eV.  No background cross  
     section is given.                                            
     Calculated 2200-m/s cross sections and res. integrals        
                  2200-m/s         res. integ.                    
      elastic     8.002 b             -                           
      capture    18.908 b           451.86 b                      
      total      26.911 b             -                           
                                                                  
 mf=3  Neutron cross sections                                     
   mt=  1  Total cross section                                    
     Spherical optical model calculation was made by using        
     casthy code [3].  Parameters are as follows,                 
            V  = 48.2-0.25*E-16.0*(N-Z)/A , r0=1.18,   a0=0.63    
            Ws = 7.84-0.51*E              , rs=1.29,   as=0.63    
            Vso= 6.0                      , rso=1.26,  aso=0.63   
                  (energies in MeV, lengths in fm).               
                                                                  
   mt=  2  Elastic scattering cross section                       
     The cross sections were obtained by subtracting a sum of     
     reaction cross sections from the total cross sections.       
                                                                  
   mt=  4,51,52,.,67,91  Inelastic scattering cross sections      
     Calculated by using egnash code [4].                         
     The direct-process component was considered for mt=51        
     from dwba calculation by dwucky code. [4,5]                  
     The level scheme is given as follows:                        
                                                                  
          no   energy(MeV) spin/parity                            
           gs    0.0000       0 +                                 
           1     0.1020       2 +                                 
           2     0.3295       4 +                                 
           3     0.6670       6 +                                 
           4     0.9007       2 +                                 
           5     1.0019       3 +                                 
           6     1.0871       0 +                                 
           7     1.0968       8 +                                 
           8     1.1280       4 +                                 
           9     1.1710       2 +                                 
          10     1.2863       4 +                                 
          11     1.3521       1 -                                 
          12     1.3567       3 -                                 
          13     1.4123       2 +                                 
          14     1.4204       0 +                                 
          15     1.4299       2 +                                 
          16     1.4597       6 +                                 
          17     1.4691       5 -                                 
                                                                  
      Levels above 1.500 MeV are assumed to be overlapping        
                                                                  
   mt=  16,17,22,28,103,104,105,107                               
           (n,2n), (n,3n), (n,n'a), (n,n'p),                      
           (n,p), (n,d), (n,t), (n,a)                             
     Calculated  using egnash [4].                                
                                                                  
   mt=102  Capture cross secton                                   
     The capture cross section is based on the statistical model  
     calculations [3]. The cross section was normalized to 253 mb 
     at 500 keV [6].  The direct and semidirect capture cross     
     sections were added above 2 MeV by using the quick gnash     
     code [7,8].                                                  
                                                                  
 mf=4  Angular distributions of secondary neutrons                
   mt=2                                                           
     Calculated with the casthy code.                             
   mt=16,17,22,28                                                 
     Assumed to be isotropic in the laboratory system.            
   mt=51,---,67,91                                                
     Calculated with the casthy code.                             
     For mt=51, the dwba component was taken into account.        
                                                                  
 mf=5  Energy distributions of secondary neutrons                 
   mt=16,17,22,28,91                                              
     Calculated with the egnash code.                             
                                                                  
 mf=12  Photon production multiplicities                          
   mt=16,17,51-67,91,102,103,107                                  
     Calculated with the egnash code.                             
                                                                  
 mf=14  Photon angular distributions                              
   mt=16,17,51-67,91,102,103,107                                  
     Assumed to be isotropic.                                     
                                                                  
 mf=15  Photon energy distributions                               
   mt=16,17,91,102,103,107                                        
                                                                  
References                                                        
  1. Landolt-Boernstein New Series I/16B (Aug 1998).              
  2. S. F. Mughabghab: "Neutron Cross Sections: Vol. 1,           
     Neutron Resonance Parameters and Thermal Cross Sections,     
     Part B: Z=61-100," Academic Press (1984).                    
  3. S. Igarasi, T. Fukahori: JAERI 1321 (1991).                  
  4. N. Yamamuro: JAERI-M 90-006 (1990).                          
  5. P.D. Kunz: Unpublished.                                      
  6. Yu.N. Trofimov: Yadernye Konstanty, (2), 11 (1989).          
  7. P.G. Young et al.: LA-12343-MS, UC-413 (1992).               
  8. N. Yamano: Private communication.