96-Cm-247

 96-CM-247 JAERI      EVAL-MAR89 T.NAKAGAWA, Y.KIKUCHI            
                      DIST-MAR89                                  
----JENDL-3.2         MATERIAL 9646                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
83-03 EVALUATION WAS BY Y.KIKUCHI(JAERI)/REF.1/.                  
89-03 RE-EVALUATION WAS MADE FOR JENDL-3 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   NUMBER OF DELAYED NEUTRONS PER FISSION                 
        SEMI-EMPIRICAL FORMULA BY TUTTLE /3/.                     
  MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                   
        THERMAL VALUE OF ZHURAVLEV ET AL./4/ AND ENERGY DEPENDENT 
        TERM OF HOWERTON /5/.                                     
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESONANCE PARAMETERS                                    
     RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 60 EV           
        EVALUATION WAS BASED ON THE EXPERIMENTAL DATA OF MOORE AND
        KEYWORTH /6/ AND BELANOVA ET AL./7/.  THE PARAMETERS OF   
        1.25-EV LEVEL WERE TAKEN FROM MUGHAGGHAB /8/.             
          RADIATIVE WIDTHS   = 0.040 EV WAS ASSUMED.              
          SCATTERING RADIUS  = 9.14 FM.                           
        A NEGATIVE RESONANCE WAS ADDED AT -0.3 EV.                
     UNRESOLVED RESONANCE REGION : 60 EV TO 30 KEV                
        PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/   
        SO AS TO REPRODUCE THE FISSION CROSS SECTION OF MOORE AND 
        KEYWORTH /6/, AND THE TOTAL AND CAPTURE CROSS SECTIONS    
        CALCULATED WITH OPTICAL AND STATISTICAL MODELS.           
          ENERGY INDEPENDENT PARAMETERS:                          
            R=9.386 FM, S2=0.86E-4, WG=0.04 EV,.                  
            WF(4-)=0.0534 EV, WF(5-)=0.5 EV,  WF(3+)=0.08 EV,     
            WF(4+)=0.68 EV,   WF(5+)=0.05 EV, WF(6+)=0.47 EV.     
                WF ESTIMATED BY SYSTEMATIC SURVEY /10/            
          ENERGY DEPENDENT PARAMETERS AT 0.9 KEV:                 
            S0=0.774E-4, S1=2.89E-4, D=1.397 EV.                  
                                                                  
  CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS      
                        2200 M/SEC      RES. INTEG.               
             TOTAL       147.8  B          -                      
             ELASTIC       8.775 B         -                      
             FISSION      81.79 B        612  B                   
             CAPTURE      57.20 B        535  B                   
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1,2,4,51-60,91,102,251   TOTAL, ELASTIC AND INELASTIC        
     SCATTERING, CAPTURE CROSS SECTIONS AND MU-L                  
        CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE        
        CASTHY/11/.                                               
        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 /12/ TO   
        REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY       
        PHILLIPS AND HOWE /13/.                                   
                                                                  
        IN THE STATISTICAL MODEL CALCULATION, COMPETING PROCESSES 
        OF FISSION, (N,2N), (N,3N) AND (N,4N), AND LEVEL          
        FLUCTUATION WERE CONSIDERED.  THE LEVEL SCHEME OF CM-247  
        WAS TAKEN FROM REF./14/.                                  
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0           9/2 -              
                    1             61.5        11/2 -              
                    2            133          13/2 -              
                    3            227           5/2 +              
                    4            266           7/2 +              
                    5            285           7/2 +              
                    6            317           9/2 +              
                    7            342           9/2 +              
                    8            404           1/2 +              
                    9            433           3/2 +              
                   10            449           5/2 +              
                CONTINUUM LEVELS ASSUMED ABOVE 479 KEV.           
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM GILBERT AND  
        CAMERON/15/.  THE GAMMA-RAY STRENGTH FUNCTION OF 2.29E-2  
        WAS DEDUCED FROM RESONANCE PARAMETERS.                    
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL/16/.                    
                                                                  
  MT=18  FISSION                                                  
        EVALUATED ON THE BASIS OF THE MEASURED DATA BY MOORE AND  
        KEYWORTH /6/ BELOW 50 KEV.  ABOVE THIS ENERGY, THE DATA OF
        FOMUSHKIN ET AL./17/ WERE ADOPTED.                        
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-60,91                                                   
        LEGENDRE COEFFICIENTS WERE GIVEN BY THE OPTICAL AND       
        STATISTICAL MODEL CALCULATIONS.                           
  MT=16,17,18,37                                                  
        ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.         
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91 EVAPORATION SPECTRUM                             
  MT=18    FISSION SPECTRUM                                       
        TEMPERATURE OF 1.47 MEV WAS ESTIMATED FROM DATA OF        
        ZHURAVLEV ET AL. /4/.                                     
                                                                  
REFERENCES                                                        
 1) KIKUCHI Y.: JAERI-M 83-236(1984).                             
 2) NAKAGAWA T.: TO BE PUBLISHED AS JAERI-M REPORT.               
 3) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).              
 4) ZHURAVLEV K.D. ET AL.: 1973 KIEV, VOL.4, 57 (1973).           
 5) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438(1977).                
 6) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656(1971)      
 7) BELANOVA T.S. ET AL.: SOV. AT. ENERGY, 47, 772(1979).         
 8) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, PART B",     
    ACADEMIC PRESS (1984).                                        
 9) KIKUCHI Y.: PRIVATE COMMUNICATION.                            
10) KIKUCHI Y. AND AN S.: J. NUCL. SCI. TECHNOL., 7, 157 (1970).  
11) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).            
12) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
13) PHILLIPS T.W. AND HOWE F.R.: NUCL. SCI. ENG., 69, 375(1979).  
14) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES , 7TH ED.,   
    (1978).                                                       
15) GILBERT A. AND CAMERON A.G.W. : CAN. J. PHYS., 43, 1446(1965).
16) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).               
17) FOMUSHKIN E.F. ET AL.: SOV. AT. ENERGY, 62, 340 (1987).