96-Cm-241

 96-CM-241 JAERI      EVAL-JUN95 T.NAKAGAWA AND T.LIU             
                      DIST-MAR02 REV2-DEC00            20001213   
----JENDL-3.3         MATERIAL 9628                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
89-03 EVALUATION FOR JENDL-3 WAS MADE BY T. NAKAGAWA(JAERI)/1/.   
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY          
      T.NAKAGAWA AND T.LIU.                                       
00-02 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA            
                                                                  
     ***** Modified parts from JENDL-3.2 *******************      
     ALL DATA OF MF'S= 2, 3, 4 AND 5                              
     *******************************************************      
                                                                  
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 /2/.                       
  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 150 EV      
    HYPOTHETICAL RESONANCE LEVELS WERE GENERATED. THEIR PARAMETERS
    WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS:          
        D-OBS = 1.8 EV,  RADIATIVE CAPTURE WIDTH = 0.040 EV,      
        S-0 = 1.0E-4, FISSION WITH = 0.5 EV, R = 9.40 FM.         
    THE FIRST RESONANCE WAS ASSUMED AT (D-OBS)*0.5 EV.  NO        
    NEGATIVE LEVELS WERE ASSUMED.                                 
                                                                  
  UNRESOLVED RESONANCES : 150 EV TO 30 KEV                        
    S0 = 0.7E-4, S1 = 2.0E-4, D-OBS =1.8 EV AND RADIATIVE WIDTH = 
    0.04 EV WERE ASSUMED.  THE FISSION WIDTH, AND S0 AND S1 WERE  
    DETERMINED WITH ASREP /4/ SO AS TO REPRODUCE ASSUMED          
    FISSION CROSS SECTIONS AND TOTAL AND CAPTURE CROSS SECTIONS   
    CALCULATED WITH CASTHY /5/.  R (9.33 FM) WAS DETERMINED TO    
    REPRODCE THE TOTAL CROSS SECTION CALCULATED WITH CASTHY.      
                                                                  
  CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS      
                   2200 M/S VALUE           RES. INT.             
      TOTAL         601.79   B                                    
      ELASTIC         7.99   B                                    
      FISSION       549.82   B              1180    B             
      CAPTURE        43.99   B                96.0  B             
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
      ----- ABOVE THE RESONANCE REGION ---                        
  MT=1 TOTAL CROSS SECTION                                        
       CALCULATED WITH CASTHY CODE /5/ BASED ON THE SHERICAL      
       OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./6/ WERE       
       USED.                                                      
                                                                  
           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)         
                                                                  
      COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE  
      TAKEN INTO ACCOUNT.  THE FOLLOWING LEVEL DENSITY PARAMETERS 
      OF GILBERT-CAMERON'S FORMULA /7/ WERE USED.                 
                                                                  
                 ISOTOPE        CM-241         CM-242             
                A(1/MEV)         28.57          28.0              
        SPIN-CUTOFF PARA.        30.22          30.0              
          PAIRING E(MEV)          0.72           1.15             
              TEMP.(MEV)          0.378          0.4              
                C(1/MEV)          5.287          2.5771           
                 EX(MEV)          3.560          4.3163           
                                                                  
        THE LEVEL SCHEME TAKEN FROM REF. /8/.                     
                                                                  
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           1/2 +              
                    1             53.          3/2 +              
                    2            103.          5/2 +              
                    3            157.          7/2 +              
                    4            255.          9/2 +              
                CONTINUUM LEVELS ASSUMED ABOVE  280 KEV.          
                                                                  
  MT= 2         ELASTIC SCATTERING                                
      CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.               
                                                                  
  MT= 4         TOTAL INELASTIC SCATTERING                        
      SUM OF MT=51, 52, 53, 54 AND 91.                            
                                                                  
  MT=16,17,18   (N,2N), (N,3N) AND FISSION                        
      STAPRE RESULTS CALCULATED BY KONSHIN /9/ WERE ADOPTED.      
      FISSION CROSS SECTION BELOW 500 KEV WERE ESTIMATED FROM THE 
      REACTION CROSS SECTIONS AND BRANCHING RATIOS TO OBTAIN THE  
      SUITABLE CAPTURE CROSS SECTIONS.                            
                                                                  
  MT=51,52,53   INELASTIC SCATTERING                              
      CALCULATED WITH ECIS /10/ AND CASTHY /5/ CODES.             
      CH.LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /11/    
      WERE USED.                                                  
           V  = 49.82 - 17 * ((N-Z) / A) - 0.3 * EN (MEV)         
           WS =  5.52 -9*((N-Z)/A)+ 0.4 * EN (MEV)     EN=<10 MEV 
              =  9.52 - 9*((N-Z)/A) (MEV)      10 =< EN =< 20 MEV 
           VSO = 6.2 (MEV)                                        
           R = RS = 1.26   , RSO = 1.12           (FM)            
           A = 0.63, AS = 0.52 , ASO = 0.47       (FM)            
           BETA-2 = 0.204 , BETA-4 = 0.051                        
                                                                  
  MT=54,91      INELASTIC SCATTERING                              
      CALCULATED WITH CASTHY CODE /5/. CROSS SECTION OF MT=91 AT  
      20 MEV WAS MODIFIED TO A SMOOTH CURVE.                      
                                                                  
  MT=102        RADIATIVE CAPTURE                                 
      CALCULATED WITH CASTHY CODE/5/.  AVERAGE RADIATIVE WIDTH =  
      0.040 EV AND D = 1.8 EV OBTAINED FROM SYSTEMATICS AND THE   
      LEVEL DENSITY PARAMETERS WERE USED.  DIRECT AND SEMI-DIRECT 
      CAPTURE CROSS SECTIONS WERE ESTIMATED WITH DSD CODE /12/.   
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2                                                            
      BELOW 300 KEV: CALCULATED WITH CASTHY CODE /5/              
      ABOVE 500 KEV: CALCULATED WITH ECIS CODE /10/               
                                                                  
  MT=16,17,18                                                     
      ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.           
                                                                  
  MT=51,52,53                                                     
      SUM OF ECIS AND CASTHY CALCULATIONS.                        
                                                                  
  MT=54,91                                                        
      CALCULATED WITH CASTHY CODE.                                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91                                                     
      CALCULATED WITH EGNASH /13/.                                
                                                                  
  MT=18                                                           
      MAXWELLIAN FISSION SPECTRUM.  TEMPERATURE ESTIMATED FROM    
      SYSTEMATICS OF HOWERTON AND DOYAS /14/.  THE RATIOS OF      
      MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM STAPRE    
      CALCULATION/9/.                                             
                                                                  
REFERENCES                                                        
 1) NAKAGAWA T.: JAERI-M 90-101 (1990).                           
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).              
 3) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977).                
 4) KIKUCHI Y., ET AL.: JAERI-DATA/CODE 99-025 (1999).            
 5) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
 6) IGNATYUK A.V. ET AL.: SOV. J. NUCL. PHYS., 42, 360 (1985).    
 7) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
 8) AKOVALI Y.A.: NUCL. DATA SHEETS, 72, 191 (1994).              
 9) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).                   
10) RAYNAL J.: IAEA SMR-9/8 (1970).                               
11) LAGRANGE CH. AND JARY J.: NEANDC(E) 198 "L" (1978).           
12) KAWANO T.: PRIVATE COMMUNICATION (1999).                      
13) YAMAMURO. N.: JAERI-M 90-006 (1990).                          
    YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).                   
14) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414        
     (1971).