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 96-Cm-246 MINSK BYEL EVAL-FEB96                                  
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 9643                               
-----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   :-   MASLOV - MINSK (DIST-FEB96)             
                                                                  
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                      V.M. MASLOV, E.Sh. SUKHOVITSKIJ,            
                      Yu.V. PORODZINSKIJ, A.B. KLEPATSKIJ,        
                      G.B.  MOROGOVSKIJ                           
 STATUS                                                           
 EVALUATION WAS MADE UNDER THE PROJECT AGREEMENT CIS-03-95        
 WITH INTERNATIONAL SCIENCE AND TECHNOLOGY CENTER (MOSCOW).       
 FINANCING PARTY OF THE CENTER FOR THE PROJECT IS JAPAN.          
 EVALUATION WAS REQUESTED BY Y.KIKUCHI (JAERI, TOKAI)             
                                                                  
 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  DELAYED NEUTRON DATA                                   
           DECAY CONSTANTS FROM BRADY ET AL./1 /                  
           NUMBER OF NEUTRONS PER FISSION FROM TUTTLE'S           
           SYSTEMATICS /2/.                                       
   MT=456  NUMBER OF NEUTRONS PER FISSION BASED ON                
           MADLAND-NIX MODEL CALCULATIONS /3/, ABOVE              
           EMISSIVE FISSION THRESHOLD A SUPERPOSITION OF          
           NEUTRON EMISSION IN (N,XNF) REACTIONS /4/ AND PROMPT   
           FISSION NEUTRONS                                       
 MF=2   RESONANCE PARAMETERS                                      
                                                                  
   MT=151  RESONANCE  PARAMETERS  (MLBW)                          
           RESOLVED RESONANCE REGION :     1.0E-5 - 400 EV        
           PARAMETERS FOR BREIT-WIGNER FORMULA ARE BASED ON       
           THE DATA OF MOORE ET AL./5/ AND MAGUIRE ET AL./6/.,    
           REVISED BY DANON ET AL./7/                             
           UNRESOLVED RESONANCE REGION : 0.4 - 43.0277 KEV.       
           ENERGY INDEPENDENT PARAMETERS:                         
              R=9.0323  FM  FROM OPTICAL MODEL CALCULATIONS       
              S1=2.769E-4   FROM OPTICAL MODEL CALCULATIONS       
              S2=1.023E-4   FROM OPTICAL MODEL CALCULATIONS       
           ENERGY   DEPENDENT PARAMETERS:                         
           S0 - DECREASES FROM 0.89E-4 (0.4KEV)TO 0.859E-4(43KEV) 
           D - SPIN DEPENDENT, NORMALIZED TO  =17.5  EV     
           WITH ACCOUNT OF LEVEL MISSING /8/                      
           WF -SPIN DEPENDENT AS DEFINED BY THE TRANSITION STATE  
           SPECTRA AT INNER AND OUTER BARRIER HUMPS,NORMALIZED    
           TO  =1.33E-03 EV TO FIT UNRESOLVED RESONANCE    
           REGION EXPERIMENTAL FISSION DATA /6,7/.                
           WG - FROM CASCADE MODEL WITH ACCOUNT OF FISSION        
           COMPETITION,SPIN DEPENDENT. NORMALIZED TO =     
           0.0347 EV.                                             
           CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE       
                       INTEGRALS.                                 
                            2200 M/SEC       RES.INTEG.           
              TOTAL         10.664 b             -                
              ELASTIC        9.208 b             -                
              FISSION        0.144 b           114.596            
              CAPTURE        1.311 b            10.281            
                                                                  
 MF=3   NEUTRON CROSS SECTIONS                                    
                                                                  
   MT=1,2,4,51-70,91,102.  TOTAL, ELASTIC AND INELASTIC           
           SCATTERING, CAPTURE CROSS SECTION                      
           TOTAL,DIRECT ELASTIC AND DIRECT INELASTIC FOR MT=51-   
           54 AND OPTICAL TRANSMISSION COEFFICIENTS ARE FROM      
           COUPLED CHANNELS CALCULATIONS.                         
           THE DEFORMED OPTICAL POTENTIAL USED:                   
           VR=46.33-0.3*E(MEV)    RR=1.26 FM  AR=0.615 FM         
           WD= 3.68+0.4*E(MEV) E <  10 MEV    RD=1.24 FM          
           WD= 7.68            E >  10 MEV    AD=0.5 FM           
           VSO=6.4  RSO=1.12  ASO=0.47  B2=0.203  B4=0.009        
           CAPTURE,COMPOUND ELASTIC AND INELASTIC BY STATISTICAL  
           MODEL, SEE MT=18-21                                    
           ABOVE NEUTRON ENERGY 5 MEV CAPTURE IS ASSUMED TO BE    
           0.001 BARN AS PREDICTED BY DIRECT AND SEMI -DIRECT     
           CAPTURE CALCULATIONS                                   
           ADOPTED LEVEL SCHEME OF CM-246 FROM NUCLEAR DATA       
           SHEETS /9/ (19 LEVELS) PLUS 2 LEVELS ADDED/10/ FOR BAND
           K,P=0+, PLUS 1 LEVEL ADDED FOR BAND K,P=1- ACCORDING   
           TO  EJK=E(BH)+A(J(J+1)-K(K+1))                         
             No       ENERGY(MEV)     SPIN-PARITY   K             
            g.s.       0.0               0   +      0             
             1         0.04258           2   +      0             
             2         0.14201           4   +      0             
             3         0.29490           6   +      0             
             4         0.50040           8   +      0             
             5         0.78207          10   +      0    *        
             6         0.84167           2   -      2             
             7         0.87643           3   -      2             
             8         0.92331           4   -      2             
             9         0.98000           5   -      2             
            10         1.05170           6   -      2             
            11         1.07885           1   -      1             
            12         1.10485           2   -      1             
            13         1.10550          12   +      0    *        
            14         1.12427           2   +      2             
            15         1.12802           3   -      1             
            16         1.12940           7   -      2             
            17         1.16549           3   +      2             
            18         1.17474           0   +      0             
            19         1.17920           8   -      2             
            20         1.19580           4   -      1    *        
            21         1.21053           2   +      0             
            * - ADDED                                             
                                                                  
          OVERLAPPING LEVELS ARE ASSUMED ABOVE 1.22 MEV           
          LEVEL DENSITY PARAMETERS: SEE MT 18-21                  
   MT=16,17.  (N,2N) AND (N,3N) CROSS SECTION                     
          FROM STATISTICAL MODEL CALCULATIONS /11/ WITH THE       
          ACCOUNT OF PRE-EQUILIBRIUM NEUTRON EMISSION:SEE MT=18-21
   MT=18,19,20,21.  FISSION CROSS SECTION                         
          BASED ON DATA OF FOMUSHKIN ET AL./12/,MAGUIRE ET AL./6/,
          REVISED BY DANON ET AL./7/.                             
          THE FIRST CHANCE FISSION MT=19 IS CALCULATED WITH       
          THE LEVEL DENSITY AND FISSION BARRIER PARAMETERS:       
                                                                  
             TRANSITION SPECTRA BAND HEADS OF 247-CM              
                                                                  
            INNER SADDLE              OUTER SADDLE                
            K,P     EKP                K,P     EKP                
           1/2+     0.0               1/2+     0.0                
           5/2+     0.08              1/2-     0.0                
           1/2-     0.05              3/2+     0.08               
           3/2-     0.0               3/2-     0.08               
                                      5/2+     0.0                
                                      5/2-     0.0                
                                                                  
                                                                  
                                                                  
             FISSION BARRIER PARAMETERS OF 247-CM                 
                                                                  
         BARRIER     BARRIER HEIGHT, MEV      CURVATURE, MEV      
          INNER            6.17                    0.7            
          OUTER            5.40                    0.6            
                                                                  
        THE CONTRIBUTION OF EMISSIVE FISSION TO THE TOTAL FISSION 
        CROSS SECTION IS CALCULATED ACCORDING TO /11,13/.         
                                                                  
 MF=4   ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS               
                                                                  
        FOR MT=2,51-54 FROM COUPLED CHANNELS CALCULATIONS         
        WITH ADDED ISOTROPIC STATISTICAL CONTRIBUTION.            
   MT=16,17,18-21,55-70,91 ISOTROPIC                              
                                                                  
 MF=5   ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS                
                                                                  
        ENERGY DISTRIBUTIONS FOR MT=16,17,18,19,20,21 WERE        
        CALCULATED BY STATISTICAL MODEL OF CASCADE NEUTRON        
        EMISSION TAKING INTO ACCOUNT THE HISTORY OF THE DECAY     
        WITH THE ALLOWANCE OF PRE-EQUILLIBRIUM EMISSION OF        
        THE FIRST NEUTRON /4/                                     
                                                                  
REFERENCES                                                        
                                                                  
 1. Brady M.C.,Wright R.Q., England T.R.,Report ORNL/CSD/TM-      
    226(1991), IAEA-NDS-102,1992                                  
 2. Tuttle R.J. Proc. Consultants Meeting on Delayed Neutron      
    Properties, 1979, Vienna, INDC(NDS)-107/G, p.29.              
 3. Madland D.G., Nix J.R., Nucl. Sci. Eng., 81, 213, (1982).     
 4. Maslov V.M., Porodzinskij Yu.V.,Sukhovitskij E.Sh., Proc.     
    Int. Conf. on Neutron Physics, 14-18 Sept., Kiev, USSR,       
    v.1, p.413, 1988.                                             
 5. Moore M.S., Keyworth G.A.: Phys. Rev. C, v3 (1971) 1656.      
 6. Maguire Jr.H.T.,Stopa C.R.S.,Block R.C.et al.:Nucl.Sci.,      
    Eng.89(1985) 293.                                             
 7. Danon Y., Slovacek R.E., Block R.C. et al.: Nucl.Sci.Eng.,    
    109 (1991) 341.                                               
 8. Porodzinskij Yu.V., Sukhovitskij E.Sh., Nuclear Constants, 4, 
    p.27, 1987 (in Russian)                                       
 9. Ellis-Akovali Y.A., Nucl. Data Sheets, 33, 119, 1981          
10. Porodzinskij Yu.V., Sukhovitskij E.Sh., Sov. J. Nucl. Phys.53,
    p.64, 1991                                                    
11. Ignatjuk A.V., Maslov V.M., Pashchenko A.B. Sov. J. Nucl.     
    Phys. 47, 224 (1988).                                         
12. Fomushkin E.F., G.F. Novoselov, Vinigradov Yu.I.,Gavrilov G.F.
    et al., Sov. J.Nucl. Phys. 36, 338 (1980).                    
13. Maslov V.M. Ann. Nucl. Energy, 20, 163, 1993.                 
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 Relevant comments taken from JEF-2.2                             
 ------------------------------------                             
                                                                  
*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-V(MAT=1346).                   *
*                                                                *
*    2-JAN-85: RADIOACTIVE DECAY DATA DELETED                     
*   10-JUN-86: ISOTROPIC MF=4,MT=18 ADDED.                        
*    6-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS                  
*                                                                *
                                                                  
           BNL,SRL,LLLEVAL-JUL76 KINSEY-ASSEMBLER(SEE COMMENTS)   
                      DIST-MAY79                       781215     
 THIS EVALUATION IS IN GENERAL A COMBINATION OF THE JULY          
 1975 EVALUATION OF BENJAMIN AND MCCROSSON AT SRL DOCUMENTED HERE 
 AND THE ENDL EVALUATION OF HOWERTON AT LLL (REF.3). BOTH SOURCES 
 WERE MODIFIED TO CONFORM TO THE ENDF/B-V FORMAT REQUIREMENTS.    
 IMPORTANT CHANGES OR ADDITIONS ARE NOTED.                        
                                                                  
MF=12,13,14,15       PHOTON PRODUCTION                            
     DATA FROM THE LLL EVALUATION WITH THE ENERGY RANGES          
     EXTENDED TO AGREE WITH MF=3.                                 
                      REFERENCES                                  
  1. L.D.GORDEEVA + G.N.SMIRENKIN,SOV.AT.EN.14(1963)562.          
  2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.              
  3. R.J.HOWERTON, UCRL 50400, VOL 15, PART A (METHODS) SEPT 75   
     AND PART B (CURVES) APR 76.                                  
  4. R.W.BENJAMIN,C.E.AHLFELD,J.A.HARVEY,+ N.W.HILL,NUCL.SCI.ENG. 
     55(1974)440.                                                 
  5. J.R.BERRETH,F.B.SIMPSON,+ B.C.RUSCHE,NUCL.SCI.ENG.49(1972)145
  6. M.S.MOORE + G.A.KEYWORTH,PHYS.REV.C,3(1971)1658.             
  7. R.W.BENJAMIN,K.W.MACMURDO,+ J.D.SPENCER,NUCL.SCI.ENG.47(1972)
     203                                                          
  8. J.HALPERIN,R.E.DRUSCHEL,+ R.E.EBY,ORNL-4437(1969)20.         
  9. R.W.BENJAMIN,V.D.VANDERVELDE,T.C.GORRELL,+ F.J.MCCROSSON,    
     PROC.CONF.NUCL.CROSS SECTIONS + TECH.,MAR.1975,WASH.,D.C.,   
     TO BE PUBLISHED.                                             
 10. C.L.DUNFORD,TI-707-130-013(1971).                            
 11. C.L.DUNFORD,AI-AEC-12931(1970).                              
 12. R.D.BAYBARZ, ET AL.,LA-4566(1971) .                          
 13. MOORE, ET AL., PR/C,3,1656,71.                               
 14. M.DRAKE + P.NICHOLS,GA-8135(1967).                           
                                                                  
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