28-Ni- 60

 28-NI- 60 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2831                               
-----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-3.1.  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/.  KUMABE'S SYSTEMATICS /4/ WAS USED.  THE PRECOM-     
        POUND/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 - 456 KEV 
        EVALUATION BASED ON THE FOLLOWING DATA.                   
           PARAMETERS IN JENDL-2 WERE MODIFIED WITH THE DATA OF   
           PEREY ET AL./6/  TWO NEGATIVE RESONANCES WERE ADDED.   
             E = -50 KEV  GAMMA-N = 12.8 KEV   GAMMA-G = 0.0 EV   
             E = -656 EV  GAMMA-N = 0.60  EV   GAMMA-G = 6.0 EV   
                                                                  
       CALCULATED 2200 M/S VALUES AND RESONANCE INTEGRALS (BARN): 
                           2200 M/S VALUE        RES. INT.        
           TOTAL              4.316                  -            
           ELASTIC            1.416                  -            
           CAPTURE            2.900                 1.467         
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  NO BACKGROUND CROSS SECTIONS ARE GIVEN BELOW 456 KEV FOR MT=1,  
  2, 102.  CROSS SECTIONS ABOVE 456 KEV WERE EVALUATED AS FOLLOWS:
                                                                  
     MT=1 : TOTAL CROSS SECTION                                   
        HIGH RESOLUSION EXPERIMENTAL DATA OF PEREY ET AL./6/ WERE 
        TRACED UP TO 1.6 MEV, AND THOSE BY STOLER ET AL./7/       
        BETWEEN 1.6 AND 2.3 MEV.  ABOVE 2.3 MEV, CROSS SECTION WAS
        CALCULATED WITH OPTICAL MODEL.  POTENTIAL PARAMETERS WERE 
        OBTAINED BY FITTING NAT-NI DATA /8/.  THE DATA MEASURED BY
        STOLER ET AL./7/ ARE REPRODUCED WELL WITH THIS SET OF OMP.
          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 SECTIONS).                    
                                                                  
     MT=3 : NONELASTIC CROSS SECTION                              
        SUM OF MT=4,16,22,28,102,103,104,105,106,107,111.         
                                                                  
     MT=16    : (N,2N)                                            
        CALCULATED WITH GNASH/9/.                                 
                                                                  
     MT=22,28,104,105,106,107,111: (N,N'A),(N,N'P),(N,D),         
                                   (N,T),(N,HE-3),(N,A),(N,2P)    
        THE CROSS SECTIONS WERE CALCULATED WITH PEGASUS/10/.  THE 
        (N,A), (N,NA) AND (N,D) CROSS SECTIONS WERE NORMALIZED TO 
        THE DATA OF GRIMES ET AL./11/ AND THE (N,T) WAS TO THE    
        DATA OF QAIM AND STOECKLIN/12/  INVERSE CROSS SECTIONS    
        WERE CALCULATED FROM THE FOLLOWING OMP'S:                 
              PROTON   = PEREY/13/                                
              ALPHA    = HUIZENGA AND IGO/14/                     
              DEUTERON = LOHR AND HAEBERLI/15/                    
              HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/16/   
                                                                  
     MT=4,52-61,91 : INELASTIC SCATTERING                         
        THE CASTHY /17/ AND GNASH /9/ CALCULATIONS WERE ADOPTED   
        FOR NEUTRON ENERGIES BELOW AND ABOVE 7 MEV, RESPECTIVELY. 
        THE CONTRIBUTION FROM THE DIRECT PROCESS WAS INCLUDED FOR 
        MT=51, 52, 53, 54, 61. FOR THE LEVEL OF MT=61, ONLY THE   
        DIRECT PROCESS WAS CONSIDERED.  THE LEVEL SCHEME USED IS  
        AS FOLLOWS:                                               
              NO  ENERGY(MEV)  SPIN-PARITY                        
             G.S    0.0          0 +                              
              1.    1.3325       2 +                              
              2.    2.1588       2 +                              
              3.    2.2849       0 +                              
              4.    2.5058       4 +                              
              5.    2.6260       3 +                              
              6.    3.1198       4 +                              
              7.    3.1240       2 +                              
              8.    3.1861       3 +                              
              9.    3.1941       1 +                              
             10.    3.2696       2 +                              
             11.    4.0397       3 -                              
          CONTINUUM LEVELS ASSUMED ABOVE 3.318 MEV.               
                                                                  
     MT=102 : CAPTURE                                             
        CALCULATED WITH CASTHY BY NORMALIZING TO 8.0 MB ANT 700   
        KEV /6/.  GAMMA-RAY STRENGTH FUNCTION IS 2.925E-5.  LEVEL 
        DENSITY PARAMETERS ARE:                                   
                              PAIRING    SPIN-CUTOFF F.           
             A(1/MEV) T(MEV) ENERGY(MEV)   (MEV**0.5)    EX(MEV)  
    ------------------------------------------------------------- 
       NI-60   7.700   1.15    2.47         6.209        8.75     
       NI-61   8.355   1.15    1.20         6.540        8.39     
    ------------------------------------------------------------- 
                                                                  
     MT=103   : (N,P)                                             
        MOST OF DATA WERE TAKEN FROM JENDL-2 WHICH REPRODUCES WELL
        THE DATA OF PAULSEN ET AL./18/, AND MODIFIED BELOW 6 MEV  
        AND AROUND 14.5 MEV BASED ON EXPERIMENTAL DATA AND GNASH  
        CALCULATION.                                              
                                                                  
     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=51-60      : CALCULATED WITH CASTHY.  DIRECT PROCESS         
                  INCLUDED IN MT=51, 52, 53, 54                   
  MT=61         : C.C. CALCULATION.                               
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,22,28,91: APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA    
                  (DDX) OF JENDL FUSION FILE.                     
                                                                  
MF=12 PHOTON MULTIPLICITIES AND TRANSITION PROBABILITY ARRAYS     
  MT=16,22,28,91,103,107:                                         
             MULTIPLICITIES CALCULATED WITH GNASH.                
  MT=102   : MULTIPLICITIES CALCULATED FROM ENERGY BALANCE.       
  MT=51-61 : TRANSITION PROBABILITY ARRAYS                        
                                                                  
MF=14 PHOTON ANGULAR DISTRIBUTIONS                                
  MT=16,22,28,51-61,91,102,103,107                                
          ISOTROPIC DISTRIBUTIONS.                                
                                                                  
MF=15 PHOTON ENERGY DISTRIBUTIONS                                 
  MT=16,22,28,91,102,103,107:                                     
          CALCULATED WITH GNASH. FOR MT=102, SPECTRA AT 1.0E-5,   
          2.53E-2, 1.0E+3 AND 1.0E+4 EV WERE CALCULATED WITH      
          CASTHY, TAKING PRIMARY TRANSITIONS.                     
                                                                  
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) PEREY C.M. ET AL.: ORNL-5893 (1982) AND PHYS. REV., C27, 2556 
    (1983).                                                       
 7) P.STOLER ET AL.: PROC. 3RD CONF. NEUTRON CROSS SECTIONS AND   
    TECHNOL., KNOXVILLE, 1971, VOL. 1, P.311 (1971).              
 8) KAWAI M. : UNPUBLISHED.                                       
 9) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).                   
10) IIJIMA S. ET AL.: JAERI-M 87-025, P.337 (1987).               
11) GRIMES S.M. ET AL.: PHYS. REV., C19, 2127 (1979).             
12) QAIM S.M. AND STOECKLIN G.: NUCL. PHYS., A257, 233 (1976).    
13) PEREY F.G: PHYS. REV. 131, 745 (1963).                        
14) HUIZENGA J.R. AND IGO G.: NUCL. PHYS. 29, 462 (1962).         
15) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS. A232, 381 (1974).      
16) 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).
17) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
18) PAULSEN A. ET AL.: NUKLEONIK, 10, 91 (1967) (EXFOR20388002).