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 96-Cm-248 JAERI      EVAL-MAR84 Y.KIKUCHI AND T.NAKAGAWA         
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 9649                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
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**         Original data taken from:  JEFF-3.1                  **
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*****************************  JEFF-3.1  *************************
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**         Original data taken from:  JEFF-3.0                  **
**                                                              **
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  05-01 NEA/OECD (Rugama) 8 delayed neutron groups                
  Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)       
                                                                  
                                                                  
*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JENDL-3.2 (DIST-SEP89) JAERI-M 84-116   
                                                                  
                          JEF-2.2 (MF12-MF15)                     
   Adopt the same LNU=2 representation for neutron multiplicities 
   Components of the energy released by fission (MT=458)          
   updated by O. Serot et al. (JEF/DOC-887).                      
   Fission Q updated consistently.                                
                                                                  
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HISTORY                                                           
84-03 NEW EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND        
      T.NAKAGAWA (JAERI).  DETAILS ARE GIVEN IN REF. /1/.         
                                                                  
MF=1  GENERAL INFORMATION                                         
  MT=451  COMMENTS AND DICTIONARY                                 
  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 /2/.                     
  MT=456  NUMBER OF NEUTRONS PER FISSION                          
        SEMI-EMPIRICAL FORMULA BY HOWERTON /3/.                   
                                                                  
MF=2  RESONANCE PARAMETERS                                        
  MT=151  RESONANCE PARAMETERS                                    
     RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 1.5 KEV         
        RESONANCE ENERGIES, NEUTRON AND RADIATIVE WIDTHS WERE     
        TAKEN FROM THE EXPERIMENTAL DATA OF BENJAMIN ET AL./4/.   
        FOR RESONANCES WHOSE RADIATIVE WIDTH WAS UNKNOWN, THE     
        AVERAGE VALUE OF 0.026 EV /4/ WAS ADOPTED.  FISSION WIDTHS
        AND THE AVERAGE FISSION WIDTH OF 0.0013 EV WERE ADOPTED   
        FROM MOORE AND KEYWORTH /5/.  THE AVERAGE FISSION WIDTH   
        WAS USED FOR ALL RESONANCES OF WHICH FISSION WIDTH HAD NOT
        BEEN MEASURED.  R=9.1 FM WAS ASSUMED TO REPRODUCE THE     
        POTENTIAL SCATTERING CROSS SECTION OF 10.4 BARNS ASSUMED  
        BY BENJAMIN ET AL./4/.  THE NEUTRON WIDTH OF THE FIRST    
        RESONANCE WAS SLIGHTLY ADJUSTED TO REPRODUCE THE CAPTURE  
        CROSS SECTION OF 2.57 BARNS AT 0.0253 EV.  BACKGROUND     
        CROSS SECTIONS WERE GIVEN ONLY FOR THE FISSION AND TOTAL  
        CROSS SECTIONS BY ASSUMING THE FORM OF 1/V.  THE THERMAL  
        CROSS SECTIONS TO BE REPRODUCED WERE ESTIMATED FROM       
        AVAILABLE EXPERIMENTAL DATA.                              
     UNRESOLVED RESONANCE REGION : 1.5 KEV TO 30 KEV              
        OBTAINED FROM OPTICAL MODEL CALCULATION:                  
          S1=3.32E-4, S2=0.844E-4, R=8.88 FM.                     
        ESTIMATED FROM RESOLVED RESONANCES:                       
          D-OBS=40.0 EV, GAM-G=26 MILLI-EV, S0=1.2E-4             
        GAM-F OBTAINED BY FITTING THE DATA OF STOPA ET AL./6/.    
                                                                  
  CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS      
                   2200 M/S VALUE           RES. INT.             
      TOTAL           9.455  B                 -                  
      ELASTIC         6.514  B                 -                  
      FISSION         0.370  B               17.5  B              
      CAPTURE         2.570  B              260.   B              
                                                                  
MF=3  NEUTRON CROSS SECTIONS                                      
     BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE 
     PARAMETERS.                                                  
                                                                  
  MT=1,2,4,51-58,91,102,251   TOTAL, ELASTIC AND INELASTIC        
     SCATTERING, CAPTURE CROSS SECTIONS AND MU-L                  
        CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE        
        CASTHY/7/.                                                
        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 /8/ TO    
        REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY       
        PHILLIPS AND HOWE /9/.                                    
                                                                  
        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-248  
        WAS TAKEN FROM REF./10/.                                  
                   NO.        ENERGY(KEV)   SPIN-PARITY           
                  G.S.             0             0 +              
                    1             43.40          2 +              
                    2            143.6           4 +              
                    3            297             6 +              
                    4            510             8 +              
                    5           1048             2 +              
                    6           1050             1 -              
                    7           1084             0 +              
                    8           1094             3 -              
                CONTINUUM LEVELS ASSUMED ABOVE 1126 KEV.          
        THE LEVEL DENSITY PARAMETERS : GILBERT AND CAMERON /11/.  
        GAMMA-RAY STRENGTH FUNCTION OF 6.5E-4 DEDUCED FROM        
        RESONANCE PARAMETERS.                                     
                                                                  
  MT=16,17,37  (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS  
        CALCULATED WITH EVAPORATION MODEL/12/.                    
                                                                  
  MT=18  FISSION                                                  
        EVALUATED ON THE BASIS OF THE MEASURED DATA BY STOPA ET   
        AL./6/ AND FOMUSHKIN ET AL./13/.                          
                                                                  
MF=4  ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS                 
  MT=2,51-58          CALCULATED WITH OPTICAL MODEL.              
  MT=16,17,18,37,91   ISOTROPIC IN THE LABORATORY SYSTEM.         
                                                                  
MF=5  ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                  
  MT=16,17,37,91      EVAPORATION SPECTRUM.                       
  MT=18               MAXWELLIAN FISSION SPECTRUM.                
                      TEMPERATURE ESTIMATED FROM SYSTEMATICS OF   
                      SMITH ET AL./14/.                           
                                                                  
REFERENCES                                                        
 1) KIKUCHI Y. AND NAKAGAWA T.: JAERI-M 84-116 (1984).            
 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).              
 3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438(1977).                
 4) BENJAMIN R.W. ET AL.: NUCL. SCI. ENG., 55, 440(1974).         
 5) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656(1971)      
 6) STOPA C.R.S. ET AL.: 1982 KIAMESHA, 1090 (1982), AND          
    MAGUIRE JR. H.T. ET AL.: NUCL. SCI. ENG., 89, 293 (1985).     
 7) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).            
 8) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).              
 9) PHILLIPS T.W. AND HOWE F.R.: NUCL. SCI. ENG., 69, 375(1979).  
10) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES , 7TH ED.    
    (1978).                                                       
11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446(1965). 
12) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).               
13) FOMUSHKIN E.F. ET AL.: SOV. J. NUCL. PHYS., 31, 19(1980).     
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).                         
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 Relevant comments from JEF-2.2                                   
 ------------------------------                                   
                                                                  
*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-V(MAT=8648).                   *
*                                                                *
*   19-AUG-84: AWR NUMBER CORRECTED IN MF=2,MT=151                
*    2-JAN-85: RADIOACTIVE DECAY DATA DELETED.                    
*    6-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS                  
*                                                                *
                                                                  
           HEDLSRLLLL EVAL-APR78 MANN,BENJAMIN,HOWERTON,ET AL.    
HEDL TME 77-54        DIST-DEC78                       790307     
            HEDL      EVAL-APR78 MANN AND SCHENTER (FAST)         
            SRL       EVAL-APR74 R.W.BENJAMIN  (THERMAL)          
            LLL       EVAL-APR78 HOWERTON (GAMMA PRODUCTION)      
           INEL       EVAL-AUG78 REICH (DECAY)                    
                                                                  
MF=1                  GENERAL INFORMATION                         
  MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF.13)          
                                                                  
MF=12,13,14,15     PHOTON PRODUCTION                              
     FILES TAKEN FROM THE LLL EVALUATIONS OF R. HOWERTON          
     DOCUMENTED IN UCRL 50400, VOL. 15, PART A (METHODS) SEPT 75  
     AND PART B (CURVES) APR 76. FILES EXTENDED TO THE ENERGY     
     RANGE 1.-5 EV TO 20 MEV AND MERGED TO THIS EVALUATION        
     AT BNL BY R. KINSEY.                                         
                                                                  
                      REFERENCES                                  
  1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.         
  2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.              
  3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.                        
  4. R.W.BENJAMIN,C.E.AHLFELD,J.A.HARVEY AND N.W.HILL,NUCL.SCI.   
     ENG.55(1974)440.                                             
  5. M.S.MOORE AND G.A.KEYWORTH,PHYS.REV.C3(1971)1658.            
  6. R.W.BENJAMIN,K.W.MACMURDO AND J.D.SPENCER,NUCL.SCI.ENG.      
     47(1972)203.                                                 
  7. R.E.DRUSCHEL,R.D.BAYBARZ,AND J.HALPERIN,ORNL-4891)23.        
  8. R.W.BENJAMIN,F.J.MCCROSSON,V.D.VANDERVELDE,AND T.C.GORRELL,  
     USERDA REPORT DP-1394(1975).                                 
 10. F. M. MANN AND R.E. SCHENTER, TRANS.AMER.NUC.SOC. 23(1976)546
     AND TO BE PUBLISHED                                          
        AND HEDL TME 77-54 (1977)                                 
 11. S. PEARLSTEIN BNL 897 (1964)                                 
 12. C. DUNFORD AND H. ALTER  NAA-SR-12271 (1967)                 
 13. R. SHER, S. FIARMAN, AND C. BECK (PRIV. COMM., OCT. 1976)    
 14. A. GILBERT AND A.G.W. CAMERON  CAN.J.PHYS. 43(1965)1446      
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