96-Cm-242

 96-CM-242 JAERI      EVAL-OCT95 T.NAKAGAWA AND T.LIU             
                      DIST-MAR02 REV2-DEC00            20001212   
----JENDL-3.3         MATERIAL 9631                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
                                                                  
HISTORY                                                           
79-03 EVALUATION FOR JENDL-2 WAS MADE BY S.IGARASI AND T.NAKAGAWA 
      (JAERI) /1/.                                                
89-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA(JAERI)/2/  
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY          
      T.NAKAGAWA AND T.LIU.                                       
00-08 MODIFICATION WAS MADE BY T.NAKAGAWA.                        
                                                                  
     ***** Modified parts from JENDL-3.2 *******************      
     (1,455)                                                      
     MF=2  Unresolved resonance parameters                        
     MF=3  All data except (3,18)                                 
     MF=4  All data                                               
     MF=5  All data                                               
     *******************************************************      
                                                                  
                                                                  
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 /3/.                       
  MT=456   NUMBER OF PROMPT NEUTRONS PER FISSION                  
      SEMI-EMPIRICAL FORMULA BY HOWERTON /4/.                     
                                                                  
MF=2,MT=151  RESONANCE PARAMETERS                                 
      ALL PARAMETERS WERE TAKEN FROM JENDL-3.2.                   
                                                                  
   RESOLVED RESONANCE REGION : 1.0E-5 EV TO 275 EV.               
          RESONANCE ENERGIES = ARTAMONOV ET AL. /5/,              
          NEUTRON WIDTHS     = ARTAMONOV ET AL. /5/,              
          RADIATIVE WIDTHS   = 0.040 EV,                          
          FISSION WIDTHS     = ALAM ET AL./6/FOR THE LOW-LYING 4  
                        LEVELS, AND THE AVERAGE VALUE OF 0.004 EV 
                        FOR OTHER LEVELS.                         
          SCATTERING RADIUS  = 9.38 FM.                           
        A NEGATIVE RESONANCE WAS ADDED AT -3.45 EV, AND ITS       
        PARAMETERS WERE ADJUSTED SO AS TO REPRODUCE WELL THE      
        THERMAL CROSS SECTIONS/7/. BACKGROUND CROSS SECTION WAS   
        GIVEN TO THE FISSION CROSS SECTION.                       
                                                                  
   UNRESOLVED RESONANCE PARAMETERS : 275 EV - 30 KEV              
        PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP /8/  
        SO AS TO REPRODUCE THE FISSION CROSS SECTION MEASURED BY  
        ALAM ET AL. /6/, AND TOTAL CROSS SECTION AT 30 KEV AND    
        CAPTURE CROSS SECTIONS FROM 6 TO 30 KEV CALCULATED WITH   
        CASTHY /9/.                                               
                                                                  
     CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.   
                          2200 M/SEC    RES. INTEG.               
             TOTAL        32.57  B       ---                      
             ELASTIC      11.61  B       ---                      
             FISSION       5.06  B       19.9 B                   
             CAPTURE      15.90  B      107   B                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1 TOTAL CROSS SECTION                                        
      CALCULATED WITH CASTHY CODE /9/ BASED ON THE SHERICAL       
      OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./10/ 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 /11/ WERE USED.                
                                                                  
                 ISOTOPE        CM-242         CM-243             
                A(1/MEV)         28.0          28.0               
        SPIN-CUTOFF PARA.        30.00         30.08              
          PAIRING E(MEV)          1.15          0.72              
              TEMP.(MEV)          0.4           0.4               
                C(1/MEV)          2.5771        7.5405            
                 EX(MEV)          4.3163        3.8863            
                                                                  
        THE LEVEL SCHEME TAKEN FROM REF./12/.                     
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0             0 +              
                    1             42.1           2 +              
                    2            138.0           4 +              
                    3            284.0           6 +              
                CONTINUUM LEVELS ASSUMED ABOVE  310 KEV.          
                                                                  
  MT= 2         ELASTIC SCATTERING                                
      CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.               
                                                                  
  MT= 4         TOTAL INELASTIC SCATTERING                        
      SUM OF MT=51, 52, 53 AND 91.                                
                                                                  
  MT=16,17      (N,2N),(N,3N)  CROSS SECTION                      
      STAPRE RESULTS CALCULATED BY KONSHIN /13/ WERE ADOPTED.     
                                                                  
  MT=18         FISSION CROSS SECTION                             
        (TAKEN FROM JENDL-3.2)                                    
      BELOW 1 MEV, CROSS SECTION WAS DETERMINED ON THE BASIS OF   
      DATA MEASURED BY ALAM ET AL./6/ AND VOROTNIKOV ET AL.       
      /14/ ABOVE 1 MEV, JENDL-2 EVALUATION WAS ADOPTED, WHICH     
      WAS BASED ON THE SHAPE OF CM-244 /15/ AND THE EMPIRICAL     
      FORMULA ON THE FISSION-CROSS-SECTION SYSTEMATICS AROUND 4   
      MEV BY BEHRENS AND HOWERTON /16/.                           
                                                                  
  MT=51,52,53   INELASTIC SCATTERING                              
      CALCULATED WITH ECIS /17/ AND CASTHY /9/ CODES.             
      CH.LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /18/    
      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=91         CONTINUUM INELASTIC SCATTERING                    
      CALCULATED WITH CASTHY CODE /9/. CROSS SECTIONS OF MT=91    
      ABOVE 10 MEV WERE MODIFIED TO A SMOOTH CURVE.               
                                                                  
  MT=102        RADIATIVE CAPTURE                                 
      CALCULATED WITH CASTHY/9/.  AVERAGE LEVEL SAPCING OF 18 EV  
      AND CAPTURE WIDTH OF 0.04 EV WERE ASSUMED.  DIRECT AND      
      SEMI-DIRECT CAPTURE CROSS SECTIONS WERE ESTIMATED WITH DSD  
      CODE /19/.                                                  
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2                                                            
      BELOW 300 KEV: CALCULATED WITH CASTHY CODE /9/              
      ABOVE 500 KEV: CALCULATED WITH ECIS CODE /17/               
                                                                  
  MT=16,17,18                                                     
      ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.           
                                                                  
  MT=51,52,53                                                     
      SUM OF ECIS AND CASTHY CALCULATIONS.                        
                                                                  
  MT=91                                                           
      CALCULATED WITH CASTHY CODE.                                
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91                                                     
      CALCULATED WITH EGNASH /20/.                                
                                                                  
  MT=18                                                           
      MAXWELLIAN FISSION SPECTRUM WITH TEMPERATURE ESTIMATED FROM 
      SYSTEMATICS OF HOWERTON AND DOYAS /21/. THE RATIOS OF       
      MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM STAPRE    
      CALCULATION/13/.                                            
                                                                  
REFERENCES                                                        
 1) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
 2) NAKAGAWA T.: JAERI-M 90-101 (1990).                           
 3) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).              
 4) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977).                
 5) ARTAMONOV V.S. ET AL. : PROC. OF 4TH ALL UNION CONF. ON       
    NEUTRON PHYSICS, KIEV (1977), VOL. 2, 257.                    
 6) ALAM B. ET AL.: NUCL. SCI. ENG., 99, 267 (1988).              
 7) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",    
    ACADEMIC PRESS (1984).                                        
 8) KIKUCHI Y. ET AL.: JAERI-DATA/CODE 99-025 (1999).             
 9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).                
10) IGNATYUK A.V. ET AL.: SOV. J. NUCL. PHYS., 42, 360 (1985).    
11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
12) SHURSHIKOV E.N. ET AL.: NUCL. DATA SHEETS, 45, 509 (1985).    
13) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).                   
14) VOROTNIKOV P.E. ET AL.: SOV. J. NUCL. PHYS., 40, 726 (1984).  
15) IGARASI S. AND NAKAGAWA T.: JAERI-M 7175 (1977).              
16) BEHRENS J.W. AND HOWERTON R.J.: NUCL. SCI. ENG., 65, 464      
    (1978).                                                       
17) RAYNAL J.: IAEA SMR-9/8 (1970).                               
18) LAGRANGE CH. AND JARY J.: NEANDC(E) 198 "L" (1978).           
19) KAWANO T.: PRIVATE COMMUNICATION (1999).                      
20) YAMAMURO. N.: JAERI-M 90-006 (1990).                          
21) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414        
     (1971).