96-Cm-242

 96-CM-242 JAERI      EVAL-MAR89 T.NAKAGAWA                       
                      DIST-SEP89                                  
----JENDL-3.2         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/. 
                                                                  
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 /3/.             
  MT=452  NUMBER OF NEUTRONS PER FISSION                          
        BASED ON THE EMPIRICAL FORMULA BY HOWERTON /4/.           
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESONANCE PARAMETERS                                    
     RESOLVED RESONANCE REGION : 1.0E-5 EV TO 275 EV.             
          RESONANCE ENERGIES = ALTAMONOV ET AL. /5/,              
          NEUTRON WIDTHS     = ALTAMONOV 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 - 40 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 40 KEV.        
          ENERGY INDEPENDENT PARAMETERS:                          
            R=9.093 FM, S0=0.92E-4, S2=0.97E-4, WG=0.04 EV.       
          ENERGY DEPENDENT PARAMETERS AT 1 KEV:                   
            S1=3.04E-4, WF=0.093 EV, D=17.16 EV.                  
                                                                  
     CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.   
                          2200 M/SEC    RES. INTEG.               
             TOTAL        32.57  B       ---                      
             ELASTIC      11.61  B       ---                      
             FISSION       5.064 B       20.0 B                   
             CAPTURE      15.90  B      109   B                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 40 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1,2,4,51-53,91,102,251   TOTAL, ELASTIC AND INELASTIC        
     SCATTERING, CAPTURE CROSS SECTIONS AND MU-L                  
        CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE        
        CASTHY/9/.                                                
        THE SPHERICAL OPTICAL POTENTIAL PARAMETERS (MEV,FM):      
           V  =43.4-0.107*EN,              R  =1.282, A  =0.60    
           WS =6.95-0.339*EN+0.0531*EN**2, RS =1.29,  B  =0.50    
                (DERIVATIVE WOODS-SAXON FORM)                     
           VSO=7.0,                        RSO=1.282, ASO=0.60    
        THIS SET OF POTENTIAL PARAMETERS WAS DETERMINED /1/ TO    
        REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY       
        PHILLIPS AND HOWE /10/.                                   
                                                                  
        IN THE STATISTICAL MODEL CALCULATION, COMPETING PROCESSES 
        OF FISSION, (N,2N) AND (N,3N), AND LEVEL FLUCTUATION WERE 
        CONSIDERED.  THE LEVEL SCHEME OF CM-242 WAS TAKEN FROM    
        ENSDF /11/:                                               
              NO.     ENERGY(MEV)        SPIN-PARITY              
             G.S.       0.0                  0 +                  
               1        0.04213              2 +                  
               2        0.138                4 +                  
               3        0.284                6 +                  
        OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.35 MEV.  THE LEVEL 
        DENSITY PARAMETERS WERE DETERMINED ON THE BASIS OF NUMBERS
        OF EXCITED LEVELS/11/.                                    
                                 CM-243    CM-242                 
                      A(1/MEV)    28.0      28.0                  
                        T(MEV)    0.40      0.40                  
                      C(1/MEV)    7.5405    2.5771                
                      E-X(MEV)    3.8863    4.3163                
       SPIN-CUTOFF(1/MEV**0.5)    30.08     30.00                 
                PAIRING E(MEV)    0.72      0.15                  
                                                                  
        AVERAGE RADIATIVE WIDTH = 0.040 EV AND D = 18 EV OBTAINED 
        FROM THE LEVEL DENSITY PARAMETERS WERE USED FOR THE       
        CAPTURE CROSS SECTION CALCULATION.                        
                                                                  
  MT=16, 17  (N,2N) AND (N,3N) CROSS SECTIONS                     
        CALCULATED WITH THE EVAPORATION MODEL BY PEARLSTEIN /12/. 
        NEUTRON EMISSION CROSS SECTION WAS ASSUMED TO BE (COMPOUND
        NUCLEUS FORMATION CROSS SECTION CALCULATED WITH OPTICAL   
        MODEL - FISSION).                                         
                                                                  
  MT=18 FISSION CROSS SECTION                                     
        BELOW 1 MEV, CROSS SECTION WAS DETERMINED ON THE BASIS OF 
        DATA MEASURED BY ALAM ET AL./6/ AND VOROTNIKOV ET AL./13/.
        ABOVE 1 MEV, JENDL-2 EVALUATION WAS ADOPTED, WHICH WAS    
        BASED ON THE SHAPE OF CM-244 /14/ AND THE EMPIRICAL       
        FORMULA ON THE FISSION-CROSS-SECTION SYSTEMATICS AROUND 4 
        MEV BY BEHRENS AND HOWERTON /15/.                         
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-53,91                                                   
        LEGENDRE COEFFICIENTS CALCULATED WITH THE OPTICAL AND     
        STATISTICAL MODELS WERE GIVEN.                            
  MT=16,17,18                                                     
        ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.         
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,91 EVAPORATION SPECTRUM.                               
  MT=18   ESTIMATED FROM Z**2/A SYSTEMATICS BY SMITH ET AL. /16/, 
          ASSUMING E(CF-252) = 2.13 MEV.                          
                                                                  
REFERENCES                                                        
 1) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
 2) NAKAGAWA T.: TO BE PUBLISHED AS JAERI-M REPORT.               
 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.: PRIVATE COMMUNICATION.                            
 9) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).            
10) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG. 69, 375 (1979).  
11) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE, AS OF JAN. 1989.
12) PEARLSTEIN S.: J. NUCL. ENERGY 27, 81 (1973).                 
13) VOROTNIKOV P.E. ET AL.: SOV. J. NUCL. PHYS., 40, 726 (1984).  
14) IGARASI S. AND NAKAGAWA T.: JAERI-M 7175 (1977).              
15) BEHRENS J.W. AND HOWERTON R.J.: NUCL. SCI. ENG., 65, 464      
    (1978).                                                       
16) SMITH A.B. ET AL.: ANL/NDM-50 (1979).