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 94-Pu-244 NEA        RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 9452                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
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*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
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*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
   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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*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-V(MAT=8444).                   *
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*   21-DEC-84: RADIOACTIVE DECAY DATA DELETED.                    
*    3-DEC-85: RESONANCE PARAM. CHANGED TO ORIGINAL SINGLE-LEVEL. 
*    5-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS                  
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           HEDL,SRL   EVAL-APR78 MANN,SCHENTER,BENJAMIN,MCCROSSON 
HEDL TME 77-54        DIST-DEC78                       790307     
           HEDL       EVAL-APR78 MANN AND SCHENTER (FAST)         
           SRL        EVAL-AUG75-BENJAMIN AND MCCROSSON (THERMAL) 
           INEL       EVAL-AUG78 REICH (DECAY)                    
MF=1                  GENERAL INFORMATION                         
  MT=452 NU  BASED ON WORK OF HOWERTON (REF. 5)                   
  MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF.6)           
MF=2                  RESONANCE PARAMETERS(0 TO 10 KEV)           
  MT=151 RESOLVED RESONANCES   RESONANCE PARAMETERS DETERMINED BY 
     THE GENRPAR CODE(REF.4) BASED ON THE SRL DATA SET.  RESOLVED 
     REGION - 0 TO 249.2 EV.                                      
         UNRESOLVED RESONANCES   SAME BASIS AS RESOLVED, WITH     
     AVERAGE RESONANCE PARAMETERS.  UNRESOLVED REGION - 249.2 EV  
     TO 10 KEV.                                                   
MF=3                  SMOOTH CROSS SECTIONS(0 TO 20 MEV)          
  MT=1  TOTAL SUM OF PARTIAL CROSS SECTIONS                       
  MT=2  ELASTIC OPTICAL MODEL CALCULATIONS (REF. 1)               
  MT=4 INELASTIC STATISTICAL MODEL CALCULATION USING 5 EXCITED    
       LEVELS AND CONTINUUM (REF. 1)                              
  MT=16 N,2N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 1)     
  MT=17 N,3N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 1)     
  MT=18 FISSION STATISTICAL MODEL CALCULATION BASED ON THE DATA OF
        BEHRENS AND BROWNE (REF 2)                                
  MT=19 (N,F) SAME AS MT=18 UNTIL (N,NF) THRESHOLD, CONSTANT      
        THEREAFTER.                                               
  MT=20 (N,NF) DIFFERENCE BETWEEN MT=18 AND MT=19                 
  MT=37 N,4N SAME AS MT=17                                        
  MT=51,...,55,91 INELASTIC STATISTICAL MODEL CALCULATION USING   
        5 EXCITED LEVELS AND CONTINUUM (REF. 1)                   
  MT=102 CAPTURE STATISTICAL MODEL CALCULATION (REF. 1)           
  MT=251,252,253 BASED ON MF=4, MT=2                              
MF=4    ANGULAR DISTRIBUTIONS                                     
  MT=2  ELASTIC  BASED ON STATISTICAL MODEL CALCULATIONS          
  MT%2         ASSUMED ISOTROPIC                                  
MF=5     ENERGY DISTRIBUTIONS                                     
  MT=16 BASED ON GILBERT AND CAMERON                              
  MT=17 SAME REFERENCE AS MT=16                                   
  MT=18,19,20 MAXWELLIAN DESCRIPTION                              
  MT=37 SAME REFERENCE AS MT=16                                   
  MT=91  BASED ON GILBERT AND CAMERON (REF. 3)                    
                      REFERENCES                                  
  1. F.M.MANN AND R.E. SCHENTER, TRANS.AMER.NUC.SOC. 23(1976)546  
        AND HEDL TME 77-54 (1977)                                 
  2. BEHRENS AND BROWNE - LLL (P.C.)                              
  3. A. GILBERT AND A.G.W. CAMERON, CAN.J.PHYS. 43(1965)1446      
  4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,       
     KNOXVILLE,TN,MARCH 2971,P.714.                               
  5. R.J. HOWERTON  NUCL.SCI.ENG. 62(1977)438.                    
  6. R. SHER, S. FIARMAN, AND C. BECK (PRIV. COMM., OCT. 1976)    
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