28-Ni- 64

 28-NI- 64 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2843                               
-----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).                             
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/.   
     -------------------------------------------------------------
                                                                  
                                                                  
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 698 KEV.  ABOVE 698 KEV UP TO 20 MEV, 
        THE OPTICAL-MODEL CALCULATION WAS PERFORMED.  POTENTIAL   
        PARAMETERS WERE OBTAINED BY FITTING NAT-NI DATA /7/:      
          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=2 : ELASTIC SCATTERING                                    
        (TOTAL) - (NONELASTIC CROSS SECTION).                     
                                                                  
     MT=3 : NONELASTIC CROSS SECTION                              
        SUM OF MT=4,16,17,22,28,102,103,104,105,107.              
                                                                  
     MT=16,17,22,28,103,104,105: (N,2N),(N,3N),(N,N'A),(N,N'P),   
                                 (N,P),(N,D),(N,T)                
        CALCULATED WITH PEGASUS/8/.  INVERSE CROSS SECTIONS       
        WERE CALCULATED FROM THE FOLLOWING OMP'S:                 
              PROTON   = PEREY/9/                                 
              ALPHA    = HUIZENGA AND IGO/10/                     
              DEUTERON = LOHR AND HAEBERLI/11/                    
              HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/12/   
                                                                  
     MT=4,51-70,91,102 : INELASTIC SCATTERING AND CAPTURE         
        CALCULATED WITH THE STATISTICAL MODEL CODE CASTHY/13/.    
        THE LEVEL SCHEME/14/ USED IS GIVEN AS FOLLOWS:            
         NO  ENERGY(MEV) SPIN-PARITY                              
         G.S    0.0          0 +                                  
          1.    1.3459       2 +                                  
          2.    2.2750       0 +                                  
          3.    2.6080       4 +                                  
          4.    2.7500       2 +                                  
          5.    2.8650       0 +                                  
          6.    2.8850       2 +                                  
          7.    2.9710       2 +                                  
          8.    3.0280       0 +                                  
          9.    3.1650       4 +                                  
         10.    3.2730       2 +                                  
         11.    3.3930       3 +                                  
         12.    3.4590       1 +                                  
         13.    3.4830       4 +                                  
         14.    3.5600       3 -                                  
         15.    3.6470       2 +                                  
         16.    3.7480       4 +                                  
         17.    3.7950       1 +                                  
         18.    3.8080       3 +                                  
         19.    3.8480       5 -                                  
         20.    3.9650       4 +                                  
        CONTINUUM LEVELS ASSUMED ABOVE 4.084 MEV.  THE GAMMA-RAY  
        STRENGTH FUNCTION OF 7.67E-6 WAS OBTAINED FROM THE CAPTURE
        CROSS SECTION DATA OF BEER AND SPENCER/15/.               
        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    
    ------------------------------------------------------------- 
                                                                  
     MT=107  : (N,A)                                              
        CALCULATED WITH PEGASUS AND MODIFIED BELOW 11 MEV ON THE  
        BASIS OF EXPERIMENTAL DATA OF QAIM ET AL./16/             
                                                                  
     MT=251  : MU-BAR                                             
        CALCULATED WITH OPTICAL MODEL.                            
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2          : CALCULATED WITH OPTICAL MODEL.                  
  MT=16,22,28,91: APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA    
                  (DDX) OF JENDL FUSION FILE.                     
  MT=51-70      : 90 DEGREE SYMMETRIC IN THE CENTER-OF-MASS       
                  SYSTEM, CALCULATED WITH CASTHY.                 
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,22,28,91: APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA    
                  (DDX) OF JENDL FUSION FILE.                     
                                                                  
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/NNDL.       
 6) FARRELL J.A. ET AL.: ANN. PHYS., 37, 367 (1966)               
    (EXFOR 11601009).                                             
 7) KAWAI M. : UNPUBLISHED.                                       
 8) IIJIMA S. ET AL.: JAERI-M 87-025, P.337 (1987).               
 9) PEREY F.G: PHYS. REV. 131, 745 (1963).                        
10) HUIZENGA J.R. AND IGO G.: NUCL. PHYS. 29, 462 (1962).         
11) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS. A232, 381 (1974).      
12) 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).
13) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
14) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES, 7TH EDI.,   
    WILEY-INTERSCIENCE (1978).                                    
15) BEER H. AND SPENCER R.R.: NUCL. PHYS., A240, 29 (1975).       
16) QAIM S.M. ET AL.: NUCL. SCI. ENG., 88, 143 (1984).