NEA Data Bank
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 56-Ba-140 NEA        RCOM-JUL82 H.GRUPPELAAR,E.MENAPACE          
 JEF/DOC-30           DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5655                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.1                  **
**                                                              **
******************************************************************
*****************************  JEFF-3.1  *************************
**                                                              **
**         Original data taken from:  JEFF-3.0                  **
**                                                              **
******************************************************************
                                                                  
*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
******************************************************************
*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENEA/CEA EVAL. (MAT=5640).            *
******************************************************************
*   16-FEB-85: DATA EXTENDED UP TO 20 MEV.                        
*   16-MAR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS                  
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
******************************************************************
                                                                  
  56-BA-140  CNEN      EVAL MAR77      CNEN-CDC-BOLOGNA           
                                                                  
    BARIUM-140           NEUTRON CROSS SECTION EVALUATION         
                                                                  
  -----------------------------MF 1-------------------------------
                                                                  
      MT 451                                                      
  2200 M/SEC CAPTURE 1.57B                                        
  RESONANCE INTEGRAL 13.7B                                        
                                                                  
  -----------------------------MF 2------------------------------ 
                                                                  
      MT 151                                                      
  CONTAINS RESOLVED PLUS UNRESOLVED MEAN PARAMETERS               
  THE RESOLVED PARAMETERS WERE RANDOMLY GENERATED BY THE PROGRAM  
  PSEUDO                                                          
                                                                  
  -----------------------------MF 3-------------------------------
                                                                  
      MT 1,2 AND 102                                              
  A SMOOTH BACKGROUND WAS ADDED TO ACCOUNT FOR NEGATIVE PEACKS    
                                                                  
      MT 251,252,253                                              
  COMPUTED BY SYSMF FROM CERBERO ANGULAR DISTRIBUTIONS.           
                                                                  
  -----------------------------MF 4-------------------------------
                                                                  
      MT 2                                                        
  TRANSFORMATION MATRIX AND LEGENDRE COEFFICIENTS COMPUTED BY     
  SYSMF FROM THE ANGULAR DISTRIBUTIONS GENERATED BY CERBERO.      
                                                                  
      MT 16,17                                                    
  ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE          
                                                                  
      MT 91 AND DISCRETE LEVELS                                   
  ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE          
                                                                  
  -----------------------------MF 5-------------------------------
                                                                  
      MT 16,17                                                    
  EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND            
  T = CONSTANT FOR THE 2ND NEUTRON                                
  T=CONSTANT FOR THE THIRD NEUTRON                                
                                                                  
      MT 91                                                       
  EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E)                
                                                                  
  ----------------------------------------------------------------
                                                                  
  COMPUTER CODES USED WERE                                        
    1)-CRESO     RESONANCE REGION DATA                            
    2)-CERBERO   CONTINUUM REGION CROSS SECTION,ANGULAR AND ENERGY
                 DISTRIBUTION DATA                                
    3)-ERINNI    HIGH ENERGY REGION CROSS SECTIONS                
    4)-SYSMF     DATA HANDLING AND FILE GENERATION                
    5)-PSEUDO    RESONANCE PARAMETERS GENERATION                  
                                                                  
  COMPLETED  ON WEDNESDAY 23 MARCH 1977 AT 21.0.15                
                                                                  
 ***************** PROGRAM LINEAR (VERSION 83-1) *****************
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.100 PER-CENT      
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