100-Fm-255

100-FM-255 TIT        EVAL-AUG87 N.TAKAGI                         
                      DIST-SEP89 REV2-JUN94                       
----JENDL-3.2         MATERIAL 9936                               
-----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/  EVALUATION BY BRADY AND       
        ENGLAND/5/ WAS ADOPTED FOR THE DECAY CONSTANTS.           
  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          3396.60  B            -                    
        ELASTIC          10.60  B            -                    
        FISSION        3360.00  B          1170  B                
        CAPTURE          26.00  B           101  B                
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 3.8 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.  
        ABOVE 3.8 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 3.8 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         7/2 +                
                    1             60         9/2 +                
        LEVELS ABOVE 94 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                                    
        MEASURED THERMAL CROSS SECTION OF 3360 BARNS WAS TAKEN    
        FROM REF./11/, AND 1/V FORM WAS ASSUMED BELOW 3.8 EV.     
        ABOVE 3.8 EV, THE SHAPE WAS ASSUMED TO BE THE SAME AS     
        BK-250 FISSION CROSS SECTION AND IT WAS NORMALIZED TO THE 
        SYSTEMATICS BY BEHRENS AND HOWERTON/12/.                  
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        MEASURED THERMAL CROSS SECTION OF 26 BARNS WAS TAKEN FROM 
        REF./11/, AND 1/V FORM WAS ASSUMED BELOW 3.8 EV.  ABOVE   
        3.8 EV, CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH    
        FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA = 0.040 EV AND    
        LEVEL SPACING = 7.6 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, 34, 1 (1981).               
10) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
11) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON      
    RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,     
    Z=61-100", ACADEMIC PRESS (1984).                             
12) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464,      
    (1978).                                                       
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).