96-Cm-240

 96-CM-240 JAERI      EVAL-OCT95 T.NAKAGAWA AND T.LIU             
                      DIST-MAR02                       20001004   
----JENDL-3.3         MATERIAL 9625                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY          
      T.NAKAGAWA AND T.LIU.                                       
00-01 RECOMPILED BY T.NAKAGAWA                                    
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  DESCRIPTIVE DATA                                        
  MT=452  NUMBER OF NEUTRONS PER FISSION                          
      SUM OF MT=455 AND MT=456                                    
  MT=455  DELAYED NEUTRON DATA                                    
      ESTIMATED FROM THE SYSTEMATICS BY TUTTLE /1/.               
  MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                   
      BASED ON THE EMPIRICAL FORMULA BY HOWERTON /2/.             
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151                                                          
  RESOLVED RESONANCE PARAMETERS (MLBW, UP TO 150 EV)              
      SINCE NO EXPETIMENTAL DATA WERE AVAILAVBLE, HYPOTHETICAL    
      RESONANCE PARAMETERS WERE GENERATED.                        
          ASSUMED PARAMETERS: S0 = 1.0E-4, D-OBS = 6.7775 EV      
               G-GAMMA = 0.036 EV, G-FISS = 0.002 EV,             
               R = 9.42 FM                                        
                                                                  
  UNRESOLVED RESONANCE PARAMETERS (UP TO 30 KEV)                  
      D-OBS AND R WERE ADJUSTED TO TOTAL AND CAPTURE CROSS        
      SECTIONS CALCULATED WITH CASTHY CODE /3/.                   
          ASSUMED PARAMETERS: S0 = 1.0E-4, S1 = 3.0E-4,           
               G-GAMMA = 0.036 EV, G-FISS = 0.002 EV              
                                                                  
  CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.      
                          2200 M/SEC    RES. INTEG.               
             TOTAL         198.4 B       ---                      
             ELASTIC        13.1 B       ---                      
             FISSION         9.8 B        44.6 B                  
             CAPTURE       175.6 B       668   B                  
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
 BELOW 30 KEV: RESONANCE REGION.                                  
                                                                  
 ABOVE 30 KEV:                                                    
                                                                  
  MT=1 TOTAL CROSS SECTION                                        
     CASTHY /3/ CALCULATION WAS ADOPTED.                          
                                                                  
   CASTHY CALCULATION                                             
   ------------------                                             
                                                                  
       SHERICAL OPTICAL POTENTIAL PARAMETERS /4/                  
                                                                  
           V = 45.036-0.3*EN                        (MEV)         
           WS= 4.115+0.4*EN                         (MEV)         
           WV= 0             , VSO = 7.5            (MEV)         
           R = RSO = 1.256   , RS  = 1.260           (FM)         
           A = ASO = 0.626   , B   = 0.555+0.0045*EN (FM)         
                                                                  
       STATISTICAL MODEL CALCULATION WITH CASTHY CODE WAS MADE    
       CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N),        
       (N,3N).                                                    
                                                                  
      THE LEVEL DENSITY PARAMETERS OF GILBERT-CAMERON'S FORMULA   
      /5/                                                         
                 ISOTOPE        CM-240         CM-241             
                A(1/MEV)         27.0          28.57              
       SPIN-CUTOFF PARA.         29.30         30.22              
          PAIRING E(MEV)          1.21          0.72              
             TEMP. (MEV)          0.4           0.378             
                C(1/MEV)          1.621         5.287             
                 EX(MEV)          4.2           3.56              
                                                                  
        THE LEVEL SCHEME TAKEN FROM REF. /6/.                     
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           0 +                
                    1             38.0         2 +                
                CONTINUUM LEVELS ASSUMED ABOVE  60  KEV.          
                                                                  
  MT= 2         ELASTIC SCATTERING                                
        CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.             
                                                                  
  MT= 4         TOTAL INELASTIC SCATTERING                        
        SUM OF MT=51 AND MT=91.                                   
                                                                  
  MT=16,17,18   (N,2N), (N,3N) AND FISSION CROSS SECTION          
        STAPRE RESULTS CALCULATED BY KONSHIN /7/ WERE ADOPTED.    
        FISSION CROSS SECTION IN THE ENERGY RANGE FROM 30 TO 500  
        KEV WAS SMOOTHLY CONECTED TO THAT OF THE UNRESOLVED       
        RESONANCE REGION.                                         
                                                                  
  MT=51, 91     PARTIAL INELASTIC SCATTERING                      
        CALCULATED WITH CASTHY CODE /3/.                          
                                                                  
  MT=102 RADIATIVE CAPTURE                                        
        CALCULATED WITH CASTHY CODE/3/.                           
        AVERAGE RADIATIVE WIDTH = 0.0358 EV AND D = 6.7775 EV     
        OBTAINED FROM SYSTEMATICS /8/ AND LEVEL DENSITY           
        PARAMETERS WERE USED.                                     
                                                                  
        DIRECT AND SEMI-DIRECT CAPTURE CROSS SECTIONS WERE        
        ESTIMATED WITH DSD CODE /9/.                              
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51,91                                                      
        CALCULATED WITH CASTHY CODE /3/.                          
  MT=16,17,18                                                     
        ISOTROPIC IN THE LABORATORY SYSTEM.                       
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91                                                     
        CALCULATED WITH EGNASH CODE /10/.                         
  MT=18                                                           
        MAXWELLIAN FISSION SPECTRUM. TEMPAREATURE WAS ESTIMATED   
        FROM SYSTEMATICS OF HOWERTON AND DOYAS /11/.  THE RATIOS  
        OF MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM      
        STAPRE CALCULATION/7/.                                    
                                                                  
                                                                  
REFERENCES                                                        
 1) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979).            
 2) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).               
 3) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 4) IGNATYUK A.V. ET AL. : SOV. J. NUCL. PHYS. 42(3) SEP. (1985). 
 5) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
 6) TULI J.K.: NUCLEAR DATA SHEETS VOL 59, NUMBER 2 (1990).       
 7) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).                   
 8) MALECKI H. ET AL.: YAD. FIZ., 37, 284 (1983).                 
 9) KAWANO T.: PRIVATE COMMUNICATION (1999).                      
10) YAMAMURO. N.: JAERI-M 90-006 (1990).                          
11) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414        
     (1971).