28-Ni- 61

 28-Ni- 61 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-MAY10                       20091112   
----JENDL-4.0         MATERIAL 2834                               
-----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/ where 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    
         (3,32)                       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),(4,32)                Isotropic distribution      
         (4,51-68)                    Isotropic distribution      
         (5,16),(5,17),(5,22),(5,28), Calculated by sincros-II    
         (5,32),(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 - 57.0keV 
        Parameters were taken from JENDL-2 except that the neutron
        width of the 64.07-keV s-wave resonance was changed from  
        54.0 eV to 535 eV /6/.                                    
        Scattering radius: 6.4 fm                                 
                                                                  
       calculated 2200 m/s values and resonance integrals (barn): 
                           2200 m/s value        res.int          
           total             11.239                 -             
           elastic            8.731                 -             
           capture            2.509                2.44           
                                                                  
mf=3  Neutron cross sections                                      
  Background cross sections were applied to the resonance region. 
  Cross sections above 57.0 keV were evaluated as follows :       
                                                                  
     mt=1 : Total cross section                                   
        High-resolution experimental data/7/ were adopted between 
        57 keV and 74.6 keV.  Above 74.6 keV up to 1.5 MeV, the   
        JENDL-3.2 data were adopted.                              
        Above 1.5 MeV, evaluation was based on the natural Ni     
        data measured by Larson et al. /8/ with unfolding         
        considering experimental resolution.                      
                                                                  
     mt=2 : Elastic scattering                                    
        (total) - (nonelastic cross sections).                    
                                                                  
     mt=16,17,22,28,32,103,104,105,106,107  (n,2n),(n,3n),(n,n'a),
                    (n,np),(n,nd),(n,p),(n,d),(n,t),(n,he-3),(n,a)
        Calculated by N. Yamamuro /9/ with sincros-II/3/.         
                                                                  
     mt=4,51-68,91 : Inelastic scattering                         
        Calculated with sincros-II.                               
        The level scheme used is as follows:                      
              no  energy(MeV) spin-parity                         
              g.s    0.0        3/2 -                             
               1.    0.0674     5/2 -                             
               2.    0.2830     1/2 -                             
               3.    0.6560     3/2 -                             
               4.    0.9086     5/2 -                             
               5.    1.0152     7/2 -                             
               6.    1.0996     3/2 -                             
               7.    1.1323     5/2 -                             
               8.    1.1852     3/2 -                             
               9.    1.4560     7/2 -                             
              10.    1.6096     5/2 -                             
              11.    1.7295     3/2 -                             
              12.    1.8077     7/2 -                             
              13.    1.9880     9/2 +                             
              14.    1.9976     3/2 -                             
              15.    2.0180     7/2 -                             
              16.    2.1216     9/2 +                             
              17.    2.1235     1/2 -                             
              18.    2.1292    11/2 -                             
                                                                  
        Continuum levels assumed above 2.4097 MeV.                
                                                                  
     mt=102: Capture                                              
        Calculted with casthy code /10/.  Taken from JENDL-3.2.   
                                                                  
     mt=111: (n,2p)                                               
        Taken from JENDL-3.2.                                     
                                                                  
     mt=203,204,205,206,207                                       
        Calculated from the cross sections given above.           
                                                                  
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=17,32      : Isotropic distribution.                         
  mt=51-68      : Isotropic distribution.                         
                                                                  
mf=5  Energy distributions of secondary neutrons                  
  mt=16,17,22,28,32,91: Calculated by N.Yamamuro /9/.             
                                                                  
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=51-68 : Transition probability arrays                        
                                                                  
mf=14 Photon angular distributions                                
  mt=16,17,22,28,51-68,91,102,103,104,107                         
          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) ENDSF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 6) Moxon M.C.: KfK-2046, p.156 (1975).                           
 7) Cho M. et al.: Proc. 2nd Int. Conf. Nucl. Data for Reactors,  
    Helsinki, 1970, Vol.1, p.619 (1970).                          
 8) Larson D.C. et al.: ORNL-TM-8203 (1983).                      
 9) Yamamuro N.: Private communication (2000).                    
10) Igarasi S. and Fukahori T.: JAERI 1321 (1991).