28-Ni- 58

 28-NI- 58 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-MAR02 REV4-MAY00            20020214   
----JENDL-3.3         MATERIAL 2825                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
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, mt=16, 22 and 28: data at threshold energies were    
       modified. mf=12, mt=16, 91 and 102 were slightly 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           
      (12,102)             Below 500 keV, revised by S.Igasasi    
      (15,102)             Below 500 keV, revised by S.Igarasi    
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL fusion file /2/  (as of Sep. 1993)                    
        Evaluated by S.Chiba (ndc/jaeri)                          
        Compiled by S.Chiba                                       
                                                                  
          All of cross sections were taken from JENDL-3.  EDX's of
        mt=16, 22, 28 and 91 were replaced by those calculated    
        with sincros-II code system/3/ in order to make the       
        agreement with the EDX of natural Ni measured by Baba et  
        al./4/ at 14.1 MeV. DDX's of continuum reactions were     
        created with f15tob program /2/.  Kumabe's systematics    
        /5/ 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/6/.   
     -------------------------------------------------------------
                                                                  
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),(3,22),(3,28),        Calculated by sincros-II    
         (3,103),(3,104),(3,105),     Calculated by sincros-II    
         (3,106),(3,107),(3,111),     Calculated by sincros-II    
         (3,203),(3,204),(3,205)      Calculated by sincros-II    
         (3,206),(3,207)              Calculated by sincros-II    
         (4,16),(4,22),(4,28),(4,91)  Deleted                     
         (5,16),(5,22),(5,28),(5,91)  Deleted                     
         (6,16),(6,22),(6,28),(6,91)  Taken from JENDL fusion file
         (6,203),(6,204),(6,205),     Taken from JENDL fusion file
         (6,206),(6,207)              Taken from JENDL fusion file
         (12,102)                     Modified                    
         (15,102)                     Modified                    
         *********************************************************
2001-03  Resonance parameters were taken from the work of Perey   
         et al./7/                                                
2002-01  Covarinaces were taken from the work of Shibata and      
         Oh./15/                                                  
                                                                  
                                                                  
mf=1,mt=451   Comments and dictionary                             
                                                                  
mf=2,mt=151   Resolved resonance parameters : 1.0e-5 eV - 812 keV 
        Based on the work of Perey et al./7/                      
        The Reich-Moore formula was employed.                     
                                                                  
       calculated 2200 m/s values and resonance integrals (barn): 
                           2200 m/s value        res. int.        
           total             29.422                 -             
           elastic           24.802                 -             
           capture            4.619                2.21           
                                                                  
mf=3  Neutron cross sections                                      
  Small ackground cross sections, which were taken from ENDF/B-VI,
  were applied to the resonance region for mt=1, 2, 102.          
  Cross sections above 812 keV were evaluated as follows:         
                                                                  
     mt=1 : Total cross section                                   
        Above 812 keV, 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=3 : Nonelastic cross section                              
        Sum of mt=4,16,22,28,102,103,104,105,106,107,111.         
                                                                  
     mt=16  (n,2n)                                                
        Evaluated by N. Yamamuro /9/ by using sincros-II code.    
                                                                  
     mt=22  (n,n'a)                                               
        Evaluated by N. Yamamuro /9/ by using sincros-II code.    
                                                                  
     mt=28  (n,n'p)                                               
        Evaluated by N. Yamamuro /9/ by using sincros-II code.    
                                                                  
     mt=4,51-65,91    Inelastic scattering                        
        The casthy /10/ and gnash /11/ calculation was adopted in 
        the neutron energy region below and above 7 MeV, respec-  
        tively.  the direct process was taken into account for mt=
        51, 52, 53, 55 and 65.  For the level of mt=65, only the  
        direct process was considered.  The level scheme used is  
        given as follows:                                         
                                                                  
                    no  energy(MeV)  spin-parity                  
                    g.s    0.0          0 +                       
                     1.    1.4545       2 +                       
                     2.    2.4591       4 +                       
                     3.    2.7755       2 +                       
                     4.    2.9018       1 +                       
                     5.    2.9424       0 +                       
                     6.    3.0376       2 +                       
                     7.    3.2634       2 +                       
                     8.    3.4203       3 +                       
                     9.    3.5240       4 +                       
                    10.    3.5309       0 +                       
                    11.    3.5934       1 +                       
                    12.    3.6200       4 +                       
                    13.    3.7744       3 +                       
                    14.    3.8983       2 +                       
                    15.    4.4753       3 -                       
               continuum levels assumed above 3.932 MeV.          
                                                                  
        Potential parameters are given as follows /12/:           
          V =51.33 - 0.331*En ,Ws=8.068 + 0.112*En ,Vso=7.0 (MeV) 
          r0=rso=1.24         ,rs=1.40                      (fm)  
          a0=aso=0.541        ,as=0.4                       (fm)  
        Surface imaginary part is in derivative Woods-Saxon form. 
                                                                  
     mt=102   Capture                                             
        Calculated with casthy.  The gamma-ray strength function  
        of 4.616e-5 was used.  Level density parameters are:      
                              pairing    spin-cutoff f.           
             a(1/MeV) T(MeV) energy(MeV)   (MeV**0.5)    Ex(MeV)  
    ------------------------------------------------------------- 
       ni-58   6.850   1.30    2.47         5.726        9.610    
       ni-59   7.126   1.325   1.20         5.907        9.250    
    ------------------------------------------------------------- 
                                                                  
     mt=103   (n,p)                                               
        Evaluated by N. Yamamuro /9/ by using sincros-II code.    
                                                                  
     mt=104,105,106,107   (n,d),(n,t),(n,he-3),(n,a)              
        Evaluated by N. Yamamuro /9/ by using sincros-II code.    
                                                                  
     mt=111   (n,2p)                                              
        The cross section was calculated using pegasus code /13/. 
        Taken from JENDL-3.2.                                     
                                                                  
     mt=203,204,205,206,207                                       
        Calculated from the cross sections mentioned above.       
                                                                  
mf=4  Angular distributions of secondary neutrons                 
  mt=2           : Calculated with optical model.                 
  mt=51-64       : Calculated with casthy.  direct process        
                   included in mt=51, 52, 53, 55.                 
  mt=65          : c.c. calculation.                              
                                                                  
mf=5  Energy-angle distributions of secondary particles           
  mt=16,22,28,91,203,204,205,206,207                              
             Taken from JENDL fusion file.                        
                                                                  
mf=12 Photon multiplicities and transition probability arrays     
  mt=16,22,28,91,103,107:                                         
             Multiplicities calculated with gnash.                
  mt=51-65 : Transition probability arrays.                       
  mt=102   : Multiplicities calculated from energy balance.       
                                                                  
mf=14 Photon angular distributions                                
  mt=16,22,28,51-65,91,102,103,107:                               
             Isotropic distributions.                             
                                                                  
mf=15 Photon energy distributions                                 
  mt=16,22,28,91,102,103,107:                                     
              Calculated with gnash. For mt=102, spectra were     
              calculated with casthy, taking primary transitions  
              at 1.0e-5, 2.53e-2, 1.0e+3 and 1.0e+4 eV.           
              Between 16 keV and 550 keV for mt=102, the          
              measurements for natural Ni /14/ are given.         
              In JENDL-3.3, for mt=102, the spectra above 1 MeV   
              were replaced by new calculations /9/               
                                                                  
mf=33 Covariances of cross sections (ref.15)                      
  mt=1                                                            
    Based on experimental data.  A chi-value was 2.99.            
  mt=2                                                            
    Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, 105, 
    and 107.                                                      
  mt=4                                                            
    Constructed from mt=51-65, 91.                                
  mt=16                                                           
    Based on experimental data.  A chi-value was 0.8.             
  mt=22, 28, 104, 105, 107                                        
    The covariances were obtained by using kalman.  A chi-value   
    was 2.67.                                                     
  mt=51-65, 91                                                    
    The covariances were obtained by usign kalman.  A chi-value   
    was 10.9.                                                     
  mt=102                                                          
    The covariances were obtained by usign kalman.  A chi-value   
    was 0.2.                                                      
  mt=103                                                          
    Based on experimental data.  A chi-value was 8.5.             
                                                                  
mf=34 Covariances of angular distributions (ref.15)               
  mt=2                                                            
    The covariances of p1 coefficients were obtained by using     
    kalman.  A chi-value was 0.84.                                
                                                                  
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) Baba M. et al.: Proc. Int. Conf. Nuclear Data for Science     
    and Technol., Mito, 1988, p.291 (1988).                       
 5) Kumabe I. et al.: Nucl. Sci. Eng., 104, 280 (1990).           
 6) ENSDF: Evaluated Nuclear Structure Data File, BNL/NNDC.       
 7) Perey C.M. et al.: ORNL/TM-10841 (1988).                      
 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).                
11) Young P.G. and Arthur E.D.: LA-6947 (1977).                   
12) Kawai M. : unpublished.                                       
13) Iijima S. et al.: JAERI-M 87-025, p.337 (1987).               
14) Igashira M.: Private communication (2000).                    
15) Shibata K. and Oh S.Y.: JAERI-Research 2000-007 (2000).