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 94-Pu-237 NEA        RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 9431                               
-----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=8437).                   *
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*   21-DEC-84: RADIOACTIVE DECAY DATA DELETED.                    
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           HEDL       EVAL-APR78 MANN AND SCHENTER (FAST)         
HEDL TME 77-54        DIST-DEC78                       790307     
           INEL       EVAL-AUG78 REICH (DECAY)                    
MF=1                  GENERAL INFORMATION                         
  MT=452 NU.  BASED ON WORK OF HOWERTON (REF. 1)                  
  MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER (REF.4)           
MF=2                  RESONANCE PARAMETERS                        
  MT=151 ONLY SCATTERING LENGTH IS GIVEN                          
MF=3                  SMOOTH CROSS SECTIONS                       
  MT=1  TOTAL  SUM OF PARTIAL CROSS SECTIONS                      
  MT=2  ELASTIC CALCULATED FROM OPTICAL MODEL (REF. 2)            
  MT=4  INELASTIC CALCULATED FROM STATISTICAL MODEL TO 10         
        EXCITED LEVELS AND THE CONTINUUM (REF. 2)                 
  MT=16 N,2N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 2)     
  MT=17 N,3N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 2)     
  MT=18 FISSION CALCULATED FROM STATISTICAL MODEL (REF. 2)        
  MT=19 (N,F) SAME AS MT=18 UNTIL (N,NF) THRESHOLD, CONSTANT      
        THEREAFTER.                                               
  MT=20 (N,NF) DIFFERENCE OF MT=18 AND MT=19                      
  MT=51,...,60,91 CALCULATED FROM STATISTICAL MODEL TO 10         
        EXCITED LEVELS AND THE CONTINUUM (REF. 2)                 
  MT=102 CAPTURE CALCULATED FROM STATISTICAL MODEL (REF. 2)       
  MT=251,252,253 BASED ON MF=4, MT=2                              
MF=4                  ANGULAR DISTRIBUTIONS                       
  MT=2  BASED ON OPTICAL MODEL CALCULATIONS                       
  MT%2  ASSUMED ISOTROPIC                                         
MF=5                  ENERGY DISTRIBUTIONS                        
  MT=16 AND 91 BASED ON PARAMETERS OF GILBERT AND CAMERON (REF. 3)
  MT=17 SAME REFERENCE AS MT=16                                   
  MT=18,19,20 MAXWELLIAN SHAPE                                    
                   REFERENCES                                     
       1. R.J. HOWERTON, NUCL.SCI.ENG. 62(1977)438                
       2. F.M. MANN AND R.E. SCHENTER, TRANS.AMER.NUCL.SOC. 23    
             (1976)546 AND HEDL TME-77-54 (1977)                  
       3. A. GILBERT AND A.G.W. CAMERON, CAN. J. PHYS. 43(1965)   
               1466.                                              
       4. R. SHER, S.FIARMAN, AND C.BECK (PRIV. COMM., OCT. 1976) 
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