26-Fe- 57

 26-Fe- 57 JNDC       EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI             
                      DIST-MAY10                       20090904   
----JENDL-4.0         MATERIAL 2634                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
 87-03  Evaluation was performed for JENDL-3.                     
 87-05  Compiled by K.Shibata (jaeri)>                            
 93-11  JENDL-3.2                                                 
        Angular distributions for mt=16,22,28,91 were converted   
        from the file-6 of the JENDL fusion file /1/ (Kalbach's   
        systematics)                                              
        Gamma production data for mt=102 were evaluated by S.     
        Igarasi (nedac).                                          
        data were compiled by K. Shibata (jaeri).                 
        ***** modified parts for JENDL-3.2 *********************  
        (4,16),(4,22),(4,28),(4,91)                               
                      Obtained from JENDL fusion file.            
        (12,102),(15,102)                                         
                      Statistical model calculations.             
        ********************************************************  
                                                                  
 2000-03   Re-evaluated and compiled by K. Shibata for JENDL-3.3  
      ********************* modified parts *********************  
      (1,451)                     revised                         
      (2,151)                     changed to Reich-Moore formula  
      (3,1)                       re-calculated                   
      (3,2)                       total - sum of partials         
      (3,102)                     preequilibrium capture included 
      (3,203),(3,207)             calculated                      
      (6,16),(6,22),(6,28),(6,91) taken from JENDL/F-99 /1/       
      (6,203),(6,207)             taken from JENDL/F-99 /1/       
      **********************************************************  
                                                                  
                                                                  
 2009-09   Re-evaluated and compiled by K. Shibata for JENDL-4    
      ********************* modified parts *********************  
      (1,451)                     revised                         
      (3,1)                       recalculated                    
      (3,4)                       sum of partials                 
      (3,51)                      replaced with ENDF/B-VII.0 below
                                  200 keV                         
      **********************************************************  
                                                                  
 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 200.0 keV                  
       The Reich-Moore formula was used.  Parameters were adopted 
       from Allen+/2/ for s-wave resonances, and Beer+/3/ for     
       p-wave resonances in 0 - 185 keV.                          
                                                                  
       calculated 2200-m/s cross sections and res. integrals.     
                       2200-m/s     res. integ.                   
          elastic       0.2021 b        -                         
          capture       2.462 b        1.43 b                     
          total         2.664 b         -                         
                                                                  
 mf=3  Neutron cross sections                                     
       Below 200 keV, background cross section was given for      
       the total and capture cross sections.                      
       Above 200 keV, the data were evaluated as follows.         
                                                                  
   mt=1    Total                                                  
       Spherical optical model calculation was made with casthy   
       code /4/.  Parameters are as follows,                      
            V  = 46.0-0.25*E              , r0=1.286, a0=0.620    
            Ws = 14.08-0.20*E             , rs=1.390. as=0.700    
            Vso= 6.00                     , rso=1.07,aso=0.620    
                  (energies in MeV unit, lengths in fm unit)      
                                                                  
   mt=2    Elastic scattering                                     
       Given as total minus nonelastic cross sections             
   mt=16,22,28,103,107  (n,2n),(n,n'a),(n,n'p),(n,p),(n,a)        
       Calculated with gnash /5/.                                 
   mt=4,51-71,91  Inelastic scattering                            
       The casthy and gnash calculations were adopted for         
       neutron energies below and above 7 MeV, respectively.      
       The level scheme used is given as follows:                 
          no.      energy(MeV)   spin-parity                      
          g.s         0.0        1/2 -                            
           1.         0.0144     3/2 -                            
           2.         0.1365     5/2 -                            
           3.         0.3668     3/2 -                            
           4.         0.7064     5/2 -                            
           5.         1.0072     7/2 -                            
           6.         1.1978     9/2 -                            
           7.         1.2654     1/2 -                            
           8.         1.3562     7/2 -                            
           9.         1.6273     3/2 -                            
          10.         1.7254     3/2 -                            
          11.         1.9893     9/2 -                            
          12.         1.9910     1/2 -                            
          13.         2.1180     5/2 -                            
          14.         2.2189     5/2 +                            
          15.         2.3300     1/2 -                            
          16.         2.3560    11/2 -                            
          17.         2.4560     9/2 +                            
          18.         2.5053     5/2 +                            
          19.         2.5643     3/2 -                            
          20.         2.6000     5/2 +                            
          21.         2.6974     1/2 -                            
       Continuum levels were assumed above 2.76 MeV.              
      ******** modifications for JENDL-4 *************************
      For mt=51, the resonance data up to 200 keV were replaced   
      with those of ENDF/B-VII.0 which were preferred by shielding
      benchmarks /7/ at 14 MeV.                                   
      ************************************************************
   mt=102  Capture                                                
        Calculated with casthy.                                   
        Pre-equilibrium capture cross sections were added /6/     
        above 5 MeV.                                              
   mt=203                                                         
        Sum of mt=28 and 103.                                     
   mt=207                                                         
        Sum of mt=22 and 107.                                     
                                                                  
 mf=4  Angular distributions of secondary neutrons                
   mt=2,51-71                                                     
       Casthy calculation                                         
                                                                  
 mf=6  Energy-angle distributions of secondary particles          
   mt=16,22,28,91                                                 
       Calculated with gnash.                                     
       Taken from JENDL/F-99.                                     
                                                                  
 mf=12 Photon multiplicities and transition probability arrays    
   mt=16,22,28,91,103,107                                         
       Multiplicities were calculated with gnash.                 
   mt=102                                                         
       Calculated with casthy.                                    
                                                                  
 mf=14 Photon angular distributions                               
   mt=16,22,28,51-71,91,102,103,107                               
       Assumed to be isotopic.                                    
                                                                  
 mf=15 Photon energy distributions                                
   mt=16,22,28,91,103,107                                         
       Calculated with gnash.                                     
   mt=102                                                         
       Calculated with casthy.                                    
                                                                  
References                                                        
 1) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).                 
 2) Allen B.J. et al.: Proc. Specialist Meeting on Neutron        
    Data of Structural Materials for Fast Reactors, Geel,         
    p. 476 (1977).                                                
 3) Beer H. and Spencer R.R.: KfK-2063 (1974).                    
 4) Igarasi S. : J. Nucl. Sci. Technol., 12, 67 (1975).           
 5) Young P.G. and Arthur E.D.: LA-6974 (1977).                   
 6) Shibata K.: Private communication (2000).                     
 7) Konno C. et al.: Private communication (2008).