96-Cm-250

 96-CM-250 TIT        EVAL-AUG87 N.TAKAGI                         
                      DIST-SEP89 REV2-JUN94                       
----JENDL-3.2         MATERIAL 9655                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF    
      TECHNOLOGY, TIT) /1/.                                       
89-08 CROSS SECTIONS WERE MODIFIED BELOW 90 EV.                   
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 CM-245 EVALUATED BY BRADY AND   
       ENGLAND/5/.                                                
  MT=456 PROMPT NEUTRONS PER FISSION                              
       BASED ON SYSTEMATICS BY MANERO AND KONSHIN/6/, AND BY      
       HOWERTON/7/.                                               
                                                                  
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            11.20  B            -                    
        ELASTIC          10.80  B            -                    
        FISSION           0.002 B            6.86 B               
        CAPTURE           0.40  B            8.23 B               
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
  MT=1  TOTAL CROSS SECTION                                       
        BELOW 90 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.   
        ABOVE 90 EV, OPTICAL MODEL CALCULATION WAS MADE WITH      
        CASTHY/8/.  THE POTENTIAL PARAMETERS/9/ 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 90 EV, THE CONSTANT CROSS SECTION OF 10.8 BARNS WAS 
        ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS     
        SECTION CALCULATED WITH OPTICAL MODEL.  ABOVE THIS ENERGY,
        OPTICAL MODEL CALCULATION WAS ADOPTED.                    
                                                                  
  MT=4,51-52,91  INELASTIC SCATTERING CROSS SECTIONS.             
        OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH   
        CASTHY/8/.  THE LEVEL SCHEME WAS TAKEN FROM REF./10/.     
                   NO         ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           0 +                
                    1             43           2 +                
                    2            142           4 +                
        LEVELS ABOVE 200 KEV WERE ASSUMED TO BE OVERLAPPING.      
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./11/.    
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL.                        
                                                                  
  MT=18  FISSION CROSS SECTION                                    
        THE CROSS SECTION WAS ASSUMED TO BE 0.1 BARN AT 0.0253 EV 
        FROM THE SYSTEMATICS OF PRINCE/12/, AND ASSUMED THE FORM  
        OF 1/V BELOW 90 EV.  AT ENERGIES ABOVE 90 EV, THE SHAPE OF
        THE CM-248 FISSION CROSS SECTION WAS ADOPTED, AND IT WAS  
        NORMALIZED TO THE SYSTEMATICS OF BEHRENS AND HOWERTON/13/.
                                                                  
  MT=102  CAPTURE CROSS SECTION                                   
        THE CROSS SECTION WAS ASSUMED TO BE 20 BARNS AT 0.0253 EV 
        FROM THE SYSTEMATICS OF PRINCE/12/ AND THE CORRELATION OF 
        THERMAL CROSS SECTIONS WITH NUMBER OF EXCESS NEUTRON.  THE
        1/V FORM WAS ASSUMED BELOW 90 EV.  ABOVE 90 EV, THE CROSS 
        SECTION WAS CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH
        FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA = 0.040 EV AND    
        LEVEL SPACING = 180 EV.                                   
                                                                  
  MT=251  MU-L                                                    
        CALCULATED WITH CASTHY.                                   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-52,91       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/14/.     
                                                                  
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) MANERO F. AND KONSHIN V.A.:  AT. ENERGY REV.,10, 637 (1972).  
 7) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991),                
 9) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
10) SCHMORAK M.R.: NUCL. DATA SHEETS, 32, 87 (1981).              
11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
12) PRINCE A.: PROC. CONF. ON NUCL. CROSS SECTIONS AND TECHNOL.,  
    WASHINGTON D.C., 4-7 MARCH, (1968), NBS SPECIAL PUBLICATION   
    299, 2, 951 (1968)                                            
13) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).