28-Ni- 62

 28-Ni- 62 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-MAY10                       20091112   
----JENDL-4.0         MATERIAL 2837                               
-----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).                             
90-10  mf=5: Data at threshold energies were modified.            
93-09  JENDL-3.2.                                                 
       Compiled by T.Nakagawa (ndc/jaeri)                         
                                                                  
     *****   modified parts for JENDL-3.2   ********************  
      (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 1.5 MeV  
         (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 - 557 keV 
        Parameters were taken from JENDL-2.                       
        Scattering radius: 6.2 fm                                 
                                                                  
       calculated 2200 m/s values and resonance integrals (barn): 
                           2200 m/s value        res.int          
           total             23.704                 -             
           elastic            9.505                 -             
           capture           14.199                6.91           
                                                                  
mf=3  Neutron cross sections                                      
  Background cross sections were applied to the resonance region. 
  Cross sections above 557 keV were evaluated as follows :        
                                                                  
     mt=1 : Total cross section                                   
        Above 557 keV, evaluation was based on the natural Ni     
        data measured by Larson et al. /6/ with unfolding         
        considering experimental resolution.                      
                                                                  
     mt=2 : Elastic scattering                                    
        (total) - (nonelastic cross section).                     
                                                                  
     mt=16,22,28,103,104,105,106,107  (n,2n),(n,n'a),(n,n'p),     
      (n,p),(n,d),(n,t),(n,he-3),(n,a)                            
        Calculated by N. Yamamuro /7/ with sincros-II/3/.         
                                                                  
     mt=4,51-64,91 : Inelastic scattering                         
        Calculated by N. Yamamuro /7/ with sincros-II/3/.         
        The level scheme used is given as follows:                
              no  energy(MeV) spin-parity                         
              g.s    0.0          0 +                             
               1.    1.1729       2 +                             
               2.    2.0486       0 +                             
               3.    2.3018       2 +                             
               4.    2.3363       4 +                             
               5.    2.8912       0 +                             
               6.    3.0585       2 +                             
               7.    3.1580       2 +                             
               8.    3.1765       4 +                             
               9.    3.2577       2 +                             
              10.    3.2620       4 +                             
              11.    3.2699       2 +                             
              12     3.2775       4 +                             
              13.    3.3703       1 +                             
              14.    3.3780                                       
        Continuum levels assumed above 3.462 MeV.                 
                                                                  
     mt=102: capture                                              
        Taken from JENDL-3.2.                                     
        Calculated with the statistical-model code casthy/8/      
        The gamma-ray strength function of 1.379e-5 was obtained  
        from the capture cross section data of Beer and Spencer   
        /9/.                                                      
        Level density parameters are:                             
                                                                  
                              pairing    spin-cutoff f.           
             a(1/MeV) T(MeV) energy(MeV)   (MeV**0.5)    Ex(MeV)  
    ------------------------------------------------------------- 
       Ni-62   8.215   1.13    2.61         6.552        9.280    
       Ni-63   9.666   0.985   1.20         7.187        7.260    
    ------------------------------------------------------------- 
                                                                  
     mt=111: (n,2p)                                               
        Taken from JENDL-3.2.                                     
        Calculated with pegasus/10/.  Inverse cross sections were 
        calculated from the following OMP's:                      
              proton   = Perey/11/                                
              alpha    = Huizenga and Igo/12/                     
              deuteron = Lohr and Haeberli/13/                    
              helium-3 and triton = Becchetti and Greenlees/14/   
                                                                  
mf=4  Angular distributions of secondary neutrons                 
  mt=2          : Calculated with optical model.                  
                  Taken from JENDL-3.2.                           
  mt=16,22,28,91: Approximately transformed from the mf=6 data    
                  (DDX) of JENDL fusion file.                     
  mt=17         : Isotropic in the lab system.                    
  mt=51-64      : 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=16,22,28,91,103,104,107:                                     
             Multiplicities calculated with sincros-II.           
  mt=102   : Multiplicities calculated from energy balance.       
  mt=51-64 : Transition probability arrays                        
                                                                  
mf=14 Photon angular distributions                                
  mt=16,22,28,51-64,91,102,103,104,107                            
          Isotropic distributions.                                
                                                                  
mf=15 Photon energy distributions                                 
  mt=16,22,28,91,102,103,104,107:                                 
          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) Larson D.C. et al.: ORNL-TM-8203 (1983).                      
 7) Yamamuro N.: Private communication (2000).                    
 8) Igarasi S. and Fukahori T.: JAERI 1321 (1991).                
 9) Beer H. and Spencer R.R.: Nucl. Phys., A240, 29 (1975).       
10) Iijima S. et al.: JAERI-M 87-025, p.337 (1987).               
11) Perey F.G: Phys. Rev. 131, 745 (1963).                        
12) Huizenga J.R. and Igo G.: Nucl. Phys. 29, 462 (1962).         
13) Lohr J.M. and Haeberli W.: Nucl. Phys. A232, 381 (1974).      
14) Becchetti F.D., Jr. and Greenlees G.W.: Polarization          
    Phenomena in Nuclear Reactions ((eds) H.H.Barshall and        
    W.Haeberli), p. 682, the University of Wisconsin Press (1971).