28-Ni- 64

 28-Ni- 64 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-MAY10                       20091112   
----JENDL-4.0         MATERIAL 2843                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
   ===========================================================    
              The data were taken from JENDL-3.3.                 
   ===========================================================    
                                                                  
                                                                  
HISTORY                                                           
87-03  Evaluation was performed for JENDL-3. Short description    
       on the evaluation is given in ref./1/                      
87-05  Compiled by K.Shibata (jaeri).                             
93-09  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (3,106), (3,111)     Deleted.                               
      (4,16-28), (4,91)    Taken from JENDL fusion file           
      (5,16-91)            Taken from JENDL fusion file           
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /2/  (as of Sep. 1993)                    
        Evaluated by S.Chiba (ndc/jaeri)                          
        Compiled by S.Chiba                                       
                                                                  
          Cross sections were taken from JENDL-3.1.  EDX's of     
        mt=16, 22, 28 and 91 were replaced by those calculated    
        with sincros-II code system/3/ because normalization      
        errors were found in the data stored in JENDL-3.1.  DDX's 
        of continuum reactions were created with f15tob program   
        /2/ in which Kumabe's systematics /4/ was used.  The      
        precompound/compound ratio was calculated by the sincros- 
        II code system.                                           
          Optical-model, level density and other parameters used  
        in the sincros-II calculation are described in ref./3/.   
        Level schemes were determined on the basis of ENSDF/5/.   
     -------------------------------------------------------------
                                                                  
2000-05  Re-evaluated by N.Yamamuro (TIT), and compiled by        
         K.Shibata (jaeri).                                       
                                                                  
         *************** modification for JENDL-3.3 **************
         (3,1)                        Re-evaluated above 557 keV  
         (3,2)                        Re-calculcated.             
         (3,16),(3,17),(3,22),(3,28), Calculated by sincros-II    
         (3,51-91)                    Calculated by sincros-II    
         (3,103),(3,104),(3,105),     Calculated by sincros-II    
         (3,106),(3,107),             Calculated by sincros-II    
         (3,203),(3,204),(3,205)      Calculated by sincros-II    
         (3,206),(3,207)              Calculated by sincros-II    
         (3,251)                      Deleted                     
         (4,17)                       Isotropic distribution      
         (4,51-68)                    Isotropic distribution      
         (5,16),(5,17),(5,22),(5,28), Calculated by sincros-II    
         (5,91)                       Calculated by sincros-II    
         (12,16-107)                  Calculated by sincros-II    
         (14,16-107)                  Isotropic distribution      
         (15,16-107)                  Calculated by sincros-II    
         *********************************************************
                                                                  
                                                                  
mf=1,mt=451   Comments and dictionary                             
                                                                  
mf=2,mt=151   Resolved resonance parameters : 1.0e-5 eV - 553 keV 
        Parameters were taken from JENDL-2.                       
        Scattering radius: 6.4 fm                                 
                                                                  
       calculated 2200 m/s values and resonance integrals (barn): 
                           2200 m/s value        res.int          
           total             1.515                  -             
           elastic           0.035                  -             
           capture           1.480                 0.820          
                                                                  
mf=3  Neutron cross sections                                      
  Background cross sections were applied to resonance region.     
  Cross sections above 553 keV were evaluated as follows :        
                                                                  
     mt=1 : Total cross section                                   
        Experimental data of Farrell et al./6/ were adopted       
        between 553 keV and 557 keV.                              
        Above 557 keV, evaluation was based on the natural Ni     
        data measured by Larson et al. /7/ with unfolding         
        considering experimental resolution.                      
                                                                  
     mt=2 : Elastic scattering                                    
        (total) - (nonelastic cross section).                     
                                                                  
     mt=16,17,22,28,103,104,105,106,107: (n,2n),(n,3n),(n,n'a),   
                          (n,n'p),(n,p),(n,d),(n,t),(n,he-3),(n,a)
        Calculated by N. Yamamuro /8/ with sincros-II/3/.         
                                                                  
     mt=4,51-70,91,102 : Inelastic scattering                     
        Calculated by N. Yamamuro /8/ with sincros-II/3/.         
        The level scheme/9/ used is given as follows:            2
         no  energy(MeV) spin-parity                              
         g.s    0.0          0 +                                  
          1.    1.3460       2 +                                  
          2.    2.2770       0 +                                  
          3.    2.6080       4 +                                  
          4.    2.8650       0 +                                  
          5     2.9710       2 +                                  
          6     3.0280       0 +                                  
          7     3.1650       4 +                                  
          8     3.2730       2 +                                  
          9.    3.3930       3 +                                  
        Continuum levels assumed above 3.459 MeV.                 
                                                                  
     mt=102  : Capture                                            
        Calculated with the statistical model code casthy/10/.    
        The gamma-ray strength function of 7.67e-6 was obtained   
        from the capture cross section data of Beer and Spencer   
        /11/.                                                     
        Level density parameters are:                             
                              pairing    spin-cutoff f.           
             a(1/MeV) T(MeV) energy(MeV)   (MeV**0.5)    Ex(MeV)  
    ------------------------------------------------------------- 
       Ni-64   9.300   1.02    2.70         7.124        8.940    
       Ni-65  10.95    0.86    1.20         7.870        6.400    
    ------------------------------------------------------------- 
                                                                  
mf=4  Angular distributions of secondary neutrons                 
  mt=2          : Calculated with optical model.                  
                  Taken from JENDL-3.2.                           
  mt=16,17,22,28,91: Approximately transformed from the mf=6 data 
                     (DDX) of JENDL fusion file.                  
  mt=51-59      : Isotropic in the center-of-mass system.         
                                                                  
mf=5  Energy distributions of secondary neutrons                  
  mt=16,17,22,28,91: Calculated with sincros-II.                  
                                                                  
mf=12 Photon multiplicities and transition probability arrays     
  mt=16,17,22,28,91,103,104,107:                                  
             Multiplicities calculated with sincros-II.           
  mt=102   : Multiplicities calculated from energy balance.       
  mt=51-59 : Transition probability arrays                        
                                                                  
mf=14 Photon angular distributions                                
  mt=16,17,22,28,51-59,91,102,103,104,107                         
          Isotropic distributions.                                
                                                                  
mf=15 Photon energy distributions                                 
  mt=16,17,22,28,91,102,103,104,107:                              
          Calculated with sincros-II.                             
                                                                  
References                                                        
 1) Iijima S. et al.: Proc. Int. Conf. Nuclear Data for Science   
    and Technol., Mito, 1988, p.627 (1988).                       
 2) Chiba S. et al.: JAERI-M 92-027, p.35 (1992).                 
 3) Yamamuro N.: JAERI-M 90-006 (1990).                           
 4) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).           
 5) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 6) Farrell J.A. et al.: Ann. Phys., 37, 367 (1966)               
    (EXFOR 11601009).                                             
 7) Larson D.C. et al.: ORNL-TM-8203 (1983).                      
 8) Yamamuro N.: Private communication (2000).                    
 9) Lederer C.M. and Shirley V.S.: Table of Isotopes, 7th ed.,    
    Wiley-Interscience (1978).                                    
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
11) Beer H. and Spencer R.R.: Nucl. Phys., A240, 29 (1975).