98-Cf-254

 98-CF-254 TIT        EVAL-AUG87 N.TAKAGI                         
                      DIST-SEP89 REV2-JUN94                       
----JENDL-3.2         MATERIAL 9867                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF    
      TECHNOLOGY, TIT) /1/.                                       
94-06 JENDL-3.2.                                                  
       NU-P, NU-D AND NU-TOTAL WERE MODIFIED.                     
      COMPILED BY T.NAKAGAWA (NDC/JAERI)                          
                                                                  
     *****   MODIFIED PARTS FOR JENDL-3.2   ********************  
      (1,452), (1,455), (1,456)                                   
     ***********************************************************  
                                                                  
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451   COMMENT AND DICTIONARY                                 
  MT=452   NUMBER OF NEUTRONS PER FISSION                         
        SUM OF NU-P NAD NU-D.                                     
  MT=455   DELAYED NEUTRONS PER FISSION                           
        AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET  
        AL./3/ AND WALDO ET AL./4/  DECAY CONSTANTS WERE ASSUMED  
        TO BE THE SAME AS THOSE OF CF-252 EVALUATED BY BRADY AND  
        ENGLAND/5/.                                               
  MT=456   PROMPT NEUTRONS PER FISSION                            
        CALCULATED FROM THE SEMI-EMPIRICAL FORMULA OF HOWERTON/6/.
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151   RESONANCE PARAMETERS                                   
    NO RESONANCE PARAMETERS WERE GIVEN.                           
                                                                  
  2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS                 
                      2200 M/S VALUE       RES. INT.              
        TOTAL            17.10  B            -                    
        ELASTIC          10.60  B            -                    
        FISSION           2.00  B           24.3 B                
        CAPTURE           4.50  B            6.5 B                
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 120 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.  
        ABOVE 120 EV, OPTICAL MODEL CALCULATION WAS MADE WITH     
        CASTHY/7/.  THE POTENTIAL PARAMETERS/8/ USED ARE AS       
        FOLLOWS,                                                  
           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)          
                                                                  
  MT=2  ELASTIC SCATTERING CROSS SECTION                          
        BELOW 120 EV, THE CONSTANT CROSS SECTION OF 10.6 BARNS WAS
        ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS     
        SECTION CALCULATED WITH OPTICAL MODEL. ABOVE THIS ENERGY, 
        OPTICAL MODEL CALCULATION WAS ADOPTED.                    
                                                                  
  MT=4,51,91  INELASTIC SCATTERING CROSS SECTIONS.                
        OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH   
        CASTHY/7/.  THE LEVEL SCHEME WAS TAKEN FROM REF./9/.      
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0.0          0 +               
                    1             45.0          2 +               
        LEVELS ABOVE 140 KEV WERE ASSUMED TO BE OVERLAPPING.      
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./10/.    
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        THE THERMAL CROSS SECTION OF 2.0 BARNS WAS ESTIMATED FROM 
        THE RATIO OF FISSION AND CAPTURE CROSS SECTIONS AT 1 EV   
        AND MEASURED CAPTURE CROSS SECTION AT 0.0253 EV.  THE FORM
        OF 1/V WAS ASSUMED BELOW 120 EV.  FOR ENERGY ABOVE 120 EV,
        THE SHAPE OF CF-252 FISSION CROSS SECTION WAS ADOPTED AND 
        IT WAS NORMALIZED TO THE SYSTEMATICS OF BEHRENS AND       
        HOWERTON/11/.                                             
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        MEASURED THERMAL CROSS SECTION OF 4.5 BARNS WAS TAKEN FROM
        REF./12/, AND 1/V FORM WAS ASSUMED BELOW 120 EV.  ABOVE   
        120 EV, THE CROSS SECTION WAS CALCULATED WITH CASTHY.  THE
        GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA
        = 0.040 EV AND LEVEL SPACING = 240 EV.                    
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51,91          CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37      ISOTROPIC IN THE LAB SYSTEM.                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRA.                        
         OBTAINED FROM LEVEL DENSITY PARAMETERS.                  
                                                                  
  MT=18               MAXWELLIAN FISSION SPECTRUM.                
         TEMPERATURE WAS ESTIMATED FROM Z**2/A DEPENDENCE/13/.    
                                                                  
REFERENCES                                                        
 1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).     
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979),            
 3) BENEDETTI G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982).         
 4) WALDO R. ET AL.: PHYS. REV., C23, 1113 (1981).                
 5) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129 (1989).
 6) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 7) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 8) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
 9) SCHMORAK M.R.: NUCL. DATA SHEETS, 32, 87 (1981).              
10) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
11) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
12) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON      
    RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,     
    Z=61-100", ACADEMIC PRESS (1984).                             
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).