96-Cm-246

 96-CM-246 JAERI      EVAL-MAR87 Y.KIKUCHI, T.NAKAGAWA            
                      DIST-SEP89                                  
----JENDL-3.2         MATERIAL 9643                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
HISTORY                                                           
87-03 NEW EVALUATION WAS MADE BY Y.KIKUCHI (JAERI) /1/.           
89-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA(JAERI) /2/.
                                                                  
MF=1                                                              
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                              
        SEMI-EMPIRICAL FORMULA BY TUTTLE /3/.                     
  MT=456  NUMBER OF PROMPT NEUTRONS PER FISSION                   
        SEMI-EMPIRICAL FORMULA BY HOWERTON /4/.                   
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESONANCE PARAMETERS                                    
     RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 330 EV          
        EVALUATION WAS BASED ON THE EXPERIMENTAL DATA /5-9/ AS    
        FOLLOWS:                                                  
          RESONANCE ENERGIES = REFS. 6 AND 8.                     
          NEUTRON WIDTHS     = REFS. 5, 6 AND 7.                  
          RADIATIVE WIDTHS   = REFS. 6 AND 8, AND AVERAGE WIDTH   
                         OF 0.031 EV WAS ASSUMED.                 
          FISSION WIDTHS     = REFS. 8 AND 9.  WF OF 4.315-EV     
                         LEVEL WAS ADJUSTED TO THE THERMAL CROSS  
                         SECTION.                                 
          SCATTERING RADIUS  = 9.85 FM. (ADJUSTED TO 11.1 B AT    
                         0.0253 EV/10/)                           
        1/V BACKGROUND DATA WERE GIVEN TO FISSION CROSS SECTION.  
     UNRESOLVED RESONANCE REGION : 330 EV TO 30 KEV               
        OBTAINED FROM OPTICAL MODEL CALCULATION:                  
          S0=0.94E-4, S1=3.17E-4, S2=0.88E-4, R=9.15 FM.          
        ESTIMATED FROM RESOLVED RESONANCES:                       
          D-OBS=31.7 EV, WG=31 MILLI-EV.                          
        WF OBTAINED BY FITTING THE DATA OF STOPA ET AL./9/.       
                                                                  
     CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS   
                        2200 M/SEC      RES. INTEG.               
             TOTAL        12.51 B          -                      
             ELASTIC      11.08 B          -                      
             FISSION       0.14 B         9.90 B                  
             CAPTURE       1.291 B        113  B                  
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1,2,4,51-79,91,102,251   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-246  
        WAS TAKEN FROM REF./14/.                                  
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0             0 -              
                    1             42.85          2 +              
                    2            141.99          4 +              
                    3            295.5           6 +              
                    4            500.0           8 +              
                    5            841.7           2 -              
                    6            876.4           3 -              
                    7            923.3           4 -              
                    8            981.0           5 -              
                    9           1051             6 -              
                   10           1079             1 -              
                   11           1105             2 -              
                   12           1124             2 +              
                   13           1128             3 -              
                   14           1129             7 -              
                   15           1165             3 +              
                   16           1175             0 +              
                   17           1179             8 -              
                   18           1211             2 +              
                   19           1220             4 +              
                   20           1250             1 -              
                   21           1289             0 +              
                   22           1300             3 -              
                   23           1318             2 +              
                   24           1349             1 -              
                   25           1367             2 -              
                   26           1379             4 +              
                   27           1452             1 +              
                   28           1478             2 +              
                   29           1509             3 +              
                CONTINUUM LEVELS ASSUMED ABOVE 1526 KEV.          
        THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM GILBERT AND  
        CAMERON /15/.  THE GAMMA-RAY STRENGTH FUNCTION OF 9.76E-4 
        DEDUCED FROM RESONANCE PARAMETERS.                        
                                                                  
  MT=16,17,37  (N,2N), (N,3N), (N,4N) REACTION CROSS SECTIONS     
        CALCULATED WITH EVAPORATION MODEL/16/.                    
                                                                  
  MT=18  FISSION                                                  
        EVALUATED ON THE BASIS OF THE MEASURED DATA BY STOPA ET   
        AL./9/ AND FOMUSHKIN ET AL./17/.                          
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-79,91                                                   
        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 1.48 MEV WAS ESTIMATED FROM DATA OF        
        ZHURAVLAV ET AL. /18/ FOR CM-245 AND CM-247.              
                                                                  
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) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438(1977).                
 5) BERRETH T.R. ET AL.: NUCL. SCI. ENG., 49, 145(1972).          
 6) BENJAMIN R.W. ET AL.: NUCL. SCI. ENG., 55, 440(1974).         
 7) BELANOVA T.S. ET AL.: SOV. AT. ENERGY, 39, 1020(1975).        
 8) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656(1971).     
 9) STOPA C.R.S. ET AL.: 1982 KIAMESHA, 1090 (1982), AND          
    MAGUIRE JR. H.T. ET AL.: NUCL. SCI. ENG., 89, 293 (1985).     
10) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, PART B",     
    ACADEMIC PRESS (1984).                                        
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) FOMSHKIN E.F. ET AL.: SOV. J. NUCL. PHYS., 31, 19(1980).      
18) ZHURAVLEV K.D. ET AL.: 1973 KIEV, VOL.4, 57 (1973).