28-Ni- 58

 28-NI- 58 NAIG       EVAL-MAR87 S.IIJIMA                         
                      DIST-SEP89 REV2-SEP93                       
----JENDL-3.2         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/.   
     -------------------------------------------------------------
                                                                  
                                                                  
MF=1,MT=451   COMMENTS AND DICTIONARY                             
                                                                  
MF=2,MT=151   RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV - 420 KEV 
        EVALUATION BASED ON THE FOLLOWING DATA.                   
           S-WAVE RESONANCE PARAMETERS FROM SYME+/7/              
           P-WAVE RESONANCE PARAMETERS FROM JENDL-2 AND SYME+/7/  
        TWO NEGATIVE RESONANCES DUE TO PEREY+/8/ WERE ADOPTED     
        WITH MODIFICATION:                                        
           E = -50  KEV   GAMMA-N = 28.0 KEV   GAMMA-G = 0.0      
           E = -6.5 KEV   GAMMA-N = 1400  EV   GAMMA-G = 2.31 EV  
        GAMMA WIDTH OF 2.0 EV AND 1.0 EV WERE ASSUMED FOR UNKNOWN 
        GAMMA WIDTHS OF S-WAVE AND P-WAVE RESONANCES, RESPEC-     
        TIVELY.                                                   
        SCATTERING RADIUS : 6.0 FM                                
                                                                  
       CALCULATED 2200 M/S VALUES AND RESONANCE INTEGRALS (BARN): 
                           2200 M/S VALUE        RES. INT.        
           TOTAL             30.754                 -             
           ELASTIC           26.251                 -             
           CAPTURE            4.503                2.16           
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  BACKGROUND CROSS SECTIONS APPLIED TO THE RESONANCE REGION FOR   
  MT=1 AND 102.  CROSS SECTIONS ABOVE 420 KEV EVALUATED AS        
  FOLLOWS:                                                        
                                                                  
     MT=1 : TOTAL CROSS SECTION                                   
        BETWEEN 420 KEV TO 677 KEV, EXPERIMENTAL DATA OF FARREL ET
        AL./9/ WERE ADOPTED.  FROM 677 KEV TO 20 MEV, CALCULATED  
        WITH OPTICAL MODEL.  POTENTIAL PARAMETERS WERE OBTAINED BY
        FITTING NAT-NI DATA /10/:                                 
          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)                                                
        MAINLY BASED ON EXPERIMENTAL DATA OF IKEDA ET AL./11/ AND 
        PAVLIK ET AL./12/                                         
                                                                  
     MT=28  (N,N'P)                                               
        OBTAINED BY SUBTRACTIONG THE (N,D) CROSS SECTION CALCULA- 
        TED WITH PEGASUS FROM THE (N,NP+PN+D)CO-57 CROSS SECTION  
        BASED ON IKEDA ET AL./11/ AND PAVLIK ET AL./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=22  (N,N'A)                                               
        CALCULATED USING THE PEGASUS CODE /17/ AND NORMALIZED TO  
        EXPERIMENTAL DATA/18/                                     
                                                                  
     MT=4,51-65,91    INELASTIC SCATTERING                        
        THE CASTHY /19/ AND GNASH /20/ 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.          
                                                                  
     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)                                               
        JENDL-2 WAS MODIFIED BY CONSIDERING EXPERIMENTAL DATA;    
        BELOW 2 MEV, DATA OF SMITH ET AL./21/, AND ABOVE 13 MEV 2 
        MEV), DATA OF IKEDA ET AL./11/ AND PAVLIK ET AL./12/      
        PEGASUS CALCULATION WAS ALSO CONSIDERED ABOVE 15 MEV.     
                                                                  
     MT=104,105,106,107,111   (N,D),(N,T),(N,HE-3),(N,A),(N,2P)   
        THE CROSS SECTIONS WERE CALCULATED USING THE PEGASUS      
        CODE /17/. THE (N,T) AND (N,A) CROSS SECTION WAS          
        NORMALIZED TO THE DATA OF QAIM AND STOECKLIN/22/ AND      
        GRIMES ET AL./18/, RESPECTIVELY.                          
                                                                  
     MT=251  : MU-BAR                                             
        CALCULATED WITH OPTICAL MODEL.                            
                                                                  
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.                              
  MT=16,22,28,91 : APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA   
                   (DDX) OF JENDL FUSION FILE.                    
                                                                  
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=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.           
                                                                  
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/NNDL.       
 7) SYME D.B. ET AL.: NEUTRON DATA OF STRUCTURAL MATERIALS FOR    
    FBR, 1977 GEEL MEET., P.703, PERGAMON PRESS(1979).            
 8) PEREY C.M. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR BASIC    
    AND APPLIED SCIENCE, SANTA FE, 1985, P.1639 (1986).           
 9) FARRELL J.A. ET AL.: ANN. PHYS., 37, 367 (1966)               
    (EXFOR11601006).                                              
10) KAWAI M. : UNPUBLISHED.                                       
11) IKEDA Y. ET AL: JAERI 1321 (1988).                            
12) PAVLIK A. ET AL.: NUCL. SCI. ENG., 90, 186 (1985).            
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) IIJIMA S. ET AL.: JAERI-M 87-025, P.337 (1987).               
18) GRIMES S.M. ET AL.: PHYS. REV., C19, 2127 (1979).             
19) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
20) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).                   
21) SMITH D.L. ET AL.: ANL/NDM-10 (1975).                         
22) QAIM S.M. AND STOECKLIN G.: NUCL. PHYS., A257, 233 (1976).