28-Ni- 0

 28-NI-  0 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-SEP89 REV2-NOV93                       
----JENDL-3.2         MATERIAL 2800                               
-----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                                                  
         GAMMA-RAY PRODUCTION DATA REVISED BY S.IGARASI (NEDAC).  
         INELASTIC SCATTERING CROSS SECTIONS BY K.SHIBATA(JAERI). 
       COMPILED BY T.NAKAGAWA (NDC/JAERI).                        
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (3,1)               557 KEV - 5 MEV                         
      (3,2)                                                       
      (3,4), (3,51-91)    RE-GROUPING INELASTIC SCATTERINGSIGS.   
      (3,103), (3,111)     SLIGHT MODIFICATION                    
      (4,16) - (4,28), (4,91)  FROM JENDL FUSION FILE             
      (5,16) - (5,91)          FROM JENDL FUSION FILE             
      ALL GAMMA-RAY PRODUCTION DATA                               
     ***********************************************************  
                                                                  
     -------------------------------------------------------------
      JENDL FUSION FILE /1/  (AS OF NOV. 1993)                    
            EVALUATED AND COMPILED BY S. CHIBA (NDC/JAERI)        
                                                                  
       CROSS SECTIONS WERE TAKEN FROM JENDL-3.1.  HOWEVER, ENERGY 
       DISTRIBUTIONS OF MT=16, 17, 22, 28 AND 91 WERE REPLACED BY 
       THOSE CALCULATED WITH SINCROS-II SYSTEM/2/.  DDXS OF       
       CONTINUUM REACTIONS WERE CREATED WITH F15TOB PROGRAM /1/.  
       THE RATIO OF PRECOMPOUND TO COMPOUND WAS TAKEN FROM        
       SINCROS-II CALCULATION.  KUMABE'S SYSTEMATICS/3/ WAS USED. 
       OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN  
       THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.  LEVEL
       SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/4/.          
     -------------------------------------------------------------
                                                                  
                                                                  
MF=1,MT=451   COMMENTS AND DICTIONARY                             
                                                                  
MF=2,MT=151   RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV - 557 KEV 
      CONSTRUCTED FROM RESONANCE PARAMETERS FOR 5 ISOTOPES WHICH  
      WERE MAINLY BASED ON THE FOLLOWING DATA:                    
                                                                  
         NI-58   SYME ET AL./5/, JENDL-2/6/                       
         NI-60   PERY ET AL./7,8/                                 
         NI-61   JENDL-2/6/, MOXON/9/                             
         NI-62   JENDL-2/6/                                       
         NI-64   JENDL-2/6/                                       
                                                                  
     CALCULATED 2200 M/S VALUES AND RESONANCE INTEGRALS (BARN):   
                           2200 M/S VALUE        RES.INT.         
           TOTAL             22.241                 -             
           ELASTIC           17.859                 -             
           CAPTURE            4.383                2.143          
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BELOW 557 KEV, BACKGROUND CROSS SECTIONS APPLIED TO MT=1, 2 AND 
  102.                                                            
                                                                  
  CROSS SECTIONS ABOVE RESONANCE REGION WERE EVALUATED AS FOLLOWS:
                                                                  
  MT=1 : TOTAL CROSS SECTION                                      
     BASED ON THE HIGH-RESOLUTION DATA OF LARSON+/10/.  THE CROSS 
     SECTION SHAPE WAS UNFOLDED BY CONSIDERING EXPERIMENTAL       
     RESOLUTION.                                                  
                                                                  
  MT=2 : ELASTIC SCATTERING                                       
     (TOTAL) - (NONELASTIC CROSS SECTIONS).                       
                                                                  
  MT=16,17,22,28,103,104,105,106,107,111: (N,2N),(N,3N),          
      (N,N'A),(N,N'P),(N,P),(N,D),(N,T),(N,HE-3),(N,A),(N,2P)     
     CONSTRUCTED FROM ISOTOPIC DATA.                              
                                                                  
  MT=4,51-70,91 : INELASTIC SCATTERING                            
     ISOTOPIC LEVELS WERE GROUPED INTO 20 LEVELS OF NATURAL       
     ELEMENT.  THE CONTRIBUTIONS FROM THE DIRECT PROCESS WERE     
     TAKEN INTO ACCOUNT FOR THE LEVELS OF MT=56, 59, 60, 61, 62,  
     63, 69, 70.                                                  
                                                                  
  MT=102 : CAPTURE                                                
     CALCULATED WITH THE STATISTICAL MODEL CODE CASTHY /11/.      
                                                                  
  MT=251  : MU-BAR                                                
        CALCULATED WITH CASTHY /11/.                              
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2              : CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,22,28,91 : TAKEN FROM JENDL FUSION FILE.               
  MT=51-70          : CALCULATED WITH CASTHY.  THE DIRECT PROCESS 
                      WAS CONSIDERED FOR MT=56,59,60,61,62,63,69, 
                      70.                                         
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,22,28,91 : TAKEN FROM JENDL FUSION FILE.               
                                                                  
MF=12 PHOTON MULTIPLICITIES                                       
  MT=102 (BELOW 2 MEV)                                            
    MULTIPLICITIES OBTAINED FROM ENERGY BALANCE.                  
                                                                  
MF=13 PHOTON PRODUCTION CROSS SECTIONS                            
  MT=3  (ABOVE 2 MEV)                                             
    CONSTRUCTED FROM THE DATA OF NI-58 AND NI-60 CALCULATED WITH  
    GNASH, AND FOLLOWING FACTOR WAS MULTIPLIED BETWEEN 2.0 AND    
    18.0 MEV, BECAUSE THEY WERE TOO LOW COMPARED WITH EXPERIMENTS 
    FROM 4.0 TO 16.0 MEV;                                         
             F(E)=EXP(0.0042(E-2.0)(18.0-E)).                     
  MT=4 (BELOW 2 MEV)                                              
    COMPOSITE DATA FROM LEVEL EXCITATION CROSS SECTIONS AND       
    BRANCHING RATIOS OF 5 ISOTOPES BELOW 2.0 MEV.                 
  MT=103, 107 (BELOW 2 MEV)                                       
    CALCULATED WITH GNASH.                                        
                                                                  
MF=14 PHOTON ANGULAR DISTRIBUTIONS                                
  MT=3,4,102,103,107: ISOTROPIC                                   
                                                                  
MF=15 PHOTON ENERGY DISTRIBUTIONS                                 
  MT=3                                                            
    CALCULATED WITH GNASH.                                        
  MT=102                                                          
    CALCULATED WITH CASTHY FOR 5 ISOTOPES, TAKING PRIMARY         
    TRANSITIONS ON NI-58 AND 60, AT 1.0E-5, 2.53E-2, 1.0E+3 AND   
    1.0E+4 EV.                                                    
  MT=103, 107                                                     
    CALCULATED WITH GNASH.                                        
                                                                  
REFERENCES                                                        
 1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).                
 2) YAMAMURO, N.: JAERI-M 90-006 (1990).                          
 3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).          
 4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.       
 5) SYME D.B. ET AL.: PROC. SPECIALIST'S MEETING ON NEUTRON DATA  
    OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, 508 DEC.     
    1977, P.703 (1979).                                           
 6) KIKUCHI Y AND SEKINE N.: JAERI-M 85-101 (1985).               
 7) PEREY F.G. ET AL.: ORNL-5893 (1982).                          
 8) PEREY C.M. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC 
    AND APPLIED SCIENCE, SANTA FE, 13-17 MAY 1985, P.1639 (1986). 
 9) MOXON M.C.: KFK-2046, P.156 (1975).                           
10) LARSON D.C. ET AL.: ORNL-TM-8203 (1983).                      
11) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).