98-Cf-249

 98-CF-249 JAERI      EVAL-MAR85 Y.KIKUCHI AND T.NAKAGAWA         
 JAERI-M 85-138       DIST-SEP89                                  
----JENDL-3.2         MATERIAL 9852                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
85-03 NEW EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND        
      T.NAKAGAWA (JAERI).  DETAILS ARE GIVEN IN REF. /1/.         
88-02 DATA WERE CHECKED AND ADOPTED FOR JENDL-3.                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENTS AND DICTIONARY                                
  MT=452   NUMBER OF NEUTRONS PER FISSION                         
             SUM OF MT'S = 455 AND 456.                           
  MT=455   DELAYED NEUTRON DATA                                   
             SEMI-EMPIRICAL FORMULA BY TUTTLE /1/.                
  MT=456   NUMBER OF PROMPT NEUTRONS PER FISSION                  
             SEMI-EMPIRICAL FORMULA BY HOWERTON /3/.              
                                                                  
MF=2,MT=151  RESONANCE PARAMETERS                                 
  RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV TO 70 EV       
    RESONANCE ENERGIES, NEUTRON AND FISSION WIDTHS WERE TAKEN     
    FROM THE EXPERIMENTAL DATA OF BENJAMIN+ /4/.  THE RADIATIVE   
    WIDTH WAS ASSUMED TO BE 0.04 EV ACCORDING TO DABBS+ /5/.      
    A NEGATIVE RESONANCE WAS ADDED SO AS TO REPRODUCE THE THERMAL 
    CROSS SECTIONS. NO BACKGROUND CORRECTION WAS APPLIED.         
                                                                  
  UNRESOLVED RESONANCES : 70 EV - 30 KEV                          
    OBTAINED FROM OPTICAL MODEL CALCULATION:                      
        S1=3.15E-4, S2=0.83E-4, R=9.08 FM.                        
    ESTIMATED FROM RESOLVED RESONANCES:                           
        DOBS=1.16 EV, GAM-G=40 MILLI-EV ,S0=1.06E-4               
    FISSION WIDTHS WERE ESTIMATED FROM THE CHANNEL THEORY OF      
    FISSION /6/. S0, S1 AND S2 VALUES WERE ADJUSTED SO AS TO      
    REPRODUCE THE FISSION CROSS SECTION MEASURED BY DABBS+ /5/.   
                                                                  
  CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS      
                   2200 M/S VALUE           RES. INT.             
      TOTAL        2176.7    B                 -                  
      ELASTIC         6.22   B                 -                  
      FISSION      1666      B               2220  B              
      CAPTURE       504.5    B                695  B              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1,2,4,51-63,91,102,251   SIG-T,SIG-EL,SIG-IN,SIG-C,MU-BAR    
        CALCULATED WITH OPTICAL AND STATISTICAL MODELS.           
        OPTICAL POTENTIAL PARAMETERS WERE OBTAINED BY FITTING THE 
        TOTAL CROSS SECTION OF PHILLIPS AND HOWE /7/ FOR AM-241:  
           V = 43.4 - 0.107*EN                      (MEV)         
           WS= 6.95 - 0.339*EN + 0.0531*EN**2       (MEV)         
           WV= 0             , VSO = 7.0            (MEV)         
           R = RSO = 1.282   , RS = 1.29            (FM)          
           A = ASO = 0.60    , B  = 0.5             (FM)          
        STATISTICAL MODEL CALCULATION WITH CASTHY CODE /8/.       
           COMPETING PROCESSES : FISSION,(N,2N),(N,3N),(N,4N).    
           LEVEL FLUCTUATION CONSIDERED.                          
        THE LEVEL SCHEME TAKEN FROM REF. /9/.                     
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           9/2 -              
                    1             62.47       11/2 -              
                    2            136.2        13/2 -              
                    3            145.0         5/2 +              
                    4            188.0         7/2 +              
                    5            219.0        15/2 -              
                    6            243.1         9/2 +              
                    7            379.5         7/2 +              
                    8            416.6         1/2 +              
                    9            437.5         9/2 +              
                   10            440.0         3/2 +              
                   11            443.0         7/2 +              
                   12            460.0         5/2 +              
                   13            500.6         9/2 +              
                CONTINUUM LEVELS ASSUMED ABOVE  550 KEV.          
        THE LEVEL DENSITY PARAMETERS : GILBERT AND CAMERON /10/.  
        GAMMA-RAY STRENGTH FUNCTION OF 3.3E-2 DEDUCED FROM        
        RESONANCE PARAMETERS.                                     
                                                                  
  MT=16,17,37      (N,2N),(N,3N),(N,4N)                           
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18            FISSION                                        
        EVALUATED ON THE BASIS OF THE MEASURED DATA BY            
        SILBERT/11/, DABBS+ /5/ AND KUPRIYANOV+ /12/.             
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-63          CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37,91   ISOTROPIC IN THE LABORATORY SYSTEM.         
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRUM.                       
  MT=18               MAXWELLIAN FISSION SPECTRUM.                
                      TEMPERATURE ESTIMATED FROM SYSTEMATICS OF   
                      SMITH+/13/.                                 
                                                                  
REFERENCES                                                        
 1) KIKUCHI Y. AND NAKAGAWA T.: JAERI-M 85-138 (1985).            
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979).            
 3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 4) BENJAMIN R.W. ET AL.: NUCL. SCI. ENG., 85, 261 (1983).        
 5) DABBS J.W.T. ET AL.: ORNL-4973, P.181 (1974).                 
 6) KIKUCHI Y. AND AN S.: J. NUCL. SCI. TECHNOL., 7, 157 (1970).  
 7) PHILLIPS T.W. AND HOWE F.R.: NUCL. SCI. ENG., 69, 375 (1979). 
 8) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).            
 9) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES , 7TH ED.    
10) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446(1965). 
11) SILBERT M.G.: NUCL. SCI. ENG., 51, 376 (1973).                
12) KUPRIYANOV V.M. ET AL.: SOV. ATOM. ENERGY, 55, 472 (1984).    
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).