68-Er-167

 68-Er-167 TIT        EVAL-SEP00 A.K.M.HARUN-AR-RASHID+           
                      DIST-MAY10                       20091112   
----JENDL-4.0         MATERIAL 6840                               
-----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).                            
2009-09 The resolved resonance paramters were modified by         
        T.Murata.  The unresolved resonance parameters were       
        obtained by K.Shibata.  The total cross sections was      
        recalculated from partial cross sections.  The data were  
        compiled by K.Shibata.                                    
                                                                  
 mf=1  General information                                        
   mt=451  Descriptive data and dictionary                        
                                                                  
 mf=2  Resonance parameters                                       
   mt=151 Resolved and unresolved resonance parameters            
     Resolved resonance region: below 591 eV                      
       The multilevel Breit-Wigner formula was used.  Resolved    
       resonance parameters from Ref. 1 or 2 (Ehi=591.0 eV).      
       Values of Gamma-gamma not given in Ref.1 or 2 are set to   
       0.089 eV.  30 resonances did not have values given for "J",
       21 are assigned to J= 3 and the remaining 9 to J= 4 by     
       random method. The value for the scattering radius is      
       8.2fm, taken from Ref.3 with small change with in the given
       error, so as to produce the close value of the thermal     
       neutron scattering cross section recommended by Mughabghab 
       (Ref. 3).  Highest energy resonance included is 590.1 eV.  
       No background cross sections were given.                   
       In JENDL-4.0, the parameters for 7.92- and 9.39-eV         
       resonances were replaced with those for 7.93- and 9.389-eV 
       resonances measured by Danon et al./11/                    
     Unresolved resonance region: 591 eV - 100 keV                
       The parameters were obtained by fitting to the calculated  
       total and capture cross sections.  The unresolved resonance
       parameters obtained should be used only for self-shielding 
       calculation.                                               
                                                                  
    Thermal cross sections and resonance integrals at 300 K       
    ----------------------------------------------------------    
                     0.0253 eV           res. integ. (*)          
                      (barns)              (barns)                
    ----------------------------------------------------------    
     Total           6.4555E+02                                   
     Elastic         1.3345E+00                                   
     n,gamma         6.4421E+02           2.9997E+03              
    ----------------------------------------------------------    
       (*) Integrated from 0.5 eV to 10 MeV.                      
                                                                  
 mf=3  Neutron cross sections                                     
   mt=1  Total cross section                                      
     Spherical optical model calculation was made by using        
     casthy code [4].  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,.,73,91  Inelastic scattering cross sections        
     Calculated by using egnash code [5,6].                       
     The direct-process component was considered for mt=51,52,62, 
     64,66 from dwba calculation by dwucky code [5,7] with a      
     weak coupling model.                                         
     The level scheme is given as follows:                        
                                                                  
           no. energy(MeV) spin-parity                            
           gs    0.0000     7/2 +                                 
           1     0.0793     9/2 +                                 
           2     0.1780    11/2 +                                 
           3     0.2078     1/2 -                                 
           4     0.2649     3/2 -                                 
           5     0.2816     5/2 -                                 
           6     0.2949    13/2 +                                 
           7     0.3466     5/2 -                                 
           8     0.4133     7/2 -                                 
           9     0.4300     7/2 -                                 
          10     0.4344    15/2 +                                 
          11     0.4420     9/2 -                                 
          12     0.5315     3/2 +                                 
          13     0.5358     9/2 -                                 
          14     0.5738     5/2 +                                 
          15     0.5874    17/2 +                                 
          16     0.6408     7/2 +                                 
          17     0.6452    11/2 -                                 
          18     0.6624    11/2 -                                 
          19     0.6679     5/2 -                                 
          20     0.6833    13/2 -                                 
          21     0.7110    11/2 +                                 
          22     0.7111     9/2 +                                 
          23     0.7453     7/2 +                                 
                                                                  
      Levels above 0.750MeV are assumed to be overlapping         
                                                                  
   mt=16,17,22,28,32,103,104,105,107   (n,2n), (n,3n), (n,n'a),   
            (n,n'p), (n,n'd)), (n,p), (n,d), (n,t), (n,a)         
     Calculated  using egnash [5,6].                              
                                                                  
   mt=102  Capture cross section                                  
      The capture cross section is based on the statistical model 
      calculations.  The measured data of Ref.8 were taken into   
      account. The direct and semidirect capture cross sections   
      were added above 2 MeV by using the quick gnash code [6,9]. 
                                                                  
 mf=4  Angular distributions of secondary neutrons                
   mt=2                                                           
      Calculated with the casthy code.                            
   mt=16,17,22,28,32,                                             
      Assumed to be isotropic in the laboratory system.           
   mt=51,---,73,91                                                
      Calculated with the casthy code.                            
      For mt=51, the dwba component was taken into account.       
                                                                  
 mf=5  Energy distributions of secondary neutrons                 
   mt=16,17,22,28,32,91                                           
      Calculated with the egnash code.                            
                                                                  
 mf=12  Photon production multiplicities                          
   mt=16,17,22,28,51-73,91,102,103,104,107                        
      Calculated with the egnash code.                            
                                                                  
 mf=14  Photon angular distributions                              
   mt=16,17,22,28,51-74,91,102,103,104,107                        
      Assumed to be isotropic.                                    
                                                                  
 mf=15  Photon energy distributions                               
   mt=16,17,22,28,91,102,103,104,107                              
      Calculated with the egnash code.                            
      For mt=102, the measured data [10] are included at 45 and   
      550 keV.                                                    
                                                                  
References                                                        
  1. Landolt-Boernstein New Series I/16B (Aug 1998).              
  2. Y. Danon et al.: Nucl. Sci. Eng., 128, 61 (1998).            
  3. S. F. Mughabghab: "Neutron Cross Sections: Vol. 1,           
     Neutron Resonance Parameters and Thermal Cross Sections,     
     Part B: Z=61-100," Academic press (1984).                    
  4. S. Igarasi, T. Fukahori: JAERI 1321 (1991).                  
  5. N. Yamamuro: JAERI-M 90-006 (1990).                          
  6. P.G. Young et al.: LA-12343-MS, UC-413 (July 1992).          
  7. P.D. Kunz: Program DWUCK4, Computational Nuclear             
     Physics 2: Nuclear Reaction; edited by K. Langanke et al.    
     Published by Springer-Verlag (1992).                         
  8. A.K.M. Harun-ar-Rashid et al.: J. Nucl. Sci. Technol., 37,   
     421 (2000).                                                  
  9. N. Yamano: Private communication.                            
 10. M. Igashira: Private communication (2001).