28-Ni- 61

 28-NI- 61 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         MATERIAL 2834                               
-----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: 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/.   
     -------------------------------------------------------------
                                                                  
                                                                  
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 20 MEV, THE    
        OPTICAL-MODEL CALCULATION WAS PERFORMED.  POTENTIAL       
        PARAMETERS WERE OBTAINED BY FITTING NAT-NI DATA/8/:       
          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=16,22,28,103,104,105,106,107,111  (N,2N),(N,N'A),(N,N'P), 
                          (N,P),(N,D),(N,T),(N,HE-3),(N,A),(N,2P) 
        CALCULATED WITH PEGASUS/9/.  INVERSE CROSS SECTIONS       
        WERE CALCULATED FROM THE FOLLOWING OMP'S:                 
              PROTON   = PEREY/10/                                
              ALPHA    = HUIZENGA AND IGO/11/                     
              DEUTERON = LOHR AND HAEBERLI/12/                    
              HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/13/   
                                                                  
     MT=4,51-70,91,102 : INELASTIC SCATTERING AND CAPTURE         
        CALCULATED WITH THE STATISTICAL MODEL CODE CASTHY /14/.   
        THE LEVEL SCHEME USED/15/ 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.    0.9088     5/2 -                             
               5.    1.0150     7/2 -                             
               6.    1.1000     3/2 -                             
               7.    1.1323     5/2 -                             
               8.    1.1857     3/2 -                             
               9.    1.4580     7/2 -                             
              10.    1.6100     5/2 -                             
              11.    1.7298     3/2 -                             
              12.    1.8080     7/2 -                             
              13.    1.9780     9/2 +                             
              14.    1.9970     3/2 -                             
              15.    2.0030     7/2 -                             
              16.    2.0190     7/2 -                             
              17.    2.1140     9/2 +                             
              18.    2.1230     1/2 -                             
              19.    2.4100     5/2 -                             
              20.    2.4660     7/2 -                             
        CONTINUUM LEVELS ASSUMED ABOVE 2.528 MEV.  THE GAMMA-RAY  
        STRENGTH FUNCTION OF 4.65E-4 WAS OBTAINED FROM THE CAPTURE
        CROSS SECTION DATA OF ERNST ET AL./16/  LEVEL DENSITY     
        PARAMETERS ARE:                                           
                              PAIRING    SPIN-CUTOFF F.           
             A(1/MEV) T(MEV) ENERGY(MEV)   (MEV**0.5)    EX(MEV)  
    ------------------------------------------------------------- 
       NI-61   8.355   1.15    1.20         6.540        8.390    
       NI-62   8.215   1.13    2.61         6.555        9.280    
    ------------------------------------------------------------- 
                                                                  
     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) 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) KAWAI M. : UNPUBLISHED.                                       
 9) IIJIMA S. ET AL.: JAERI-M 87-025, P.337 (1987).               
10) PEREY F.G: PHYS. REV. 131, 745 (1963).                        
11) HUIZENGA J.R. AND IGO G.: NUCL. PHYS. 29, 462 (1962).         
12) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS. A232, 381 (1974).      
13) 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).
14) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
15) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES, 7TH EDI.,   
    WILEY-INTERSCIENCE (1978).                                    
16) ERNST A. ET AL.: PROC. 2ND INT. CONF. NUCL. DATA FOR          
    REACTORS, HELSINKI, 1970, VOL.1, P.633 (1970).