NEA Data Bank
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 58-Ce-141 NEA        RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE          
 JEF/DOC-30           DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5840                               
-----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 CNEN/CEA(MAT=5841) AND TRANSLATED     *
*     TO ENDF/B-V FORMAT AT THE NEA DATA BANK .                  *
******************************************************************
*   16-FEB-85: DATA EXTENDED UP TO 20 MEV.                        
*   17-MAR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
*              BREIT-WIGNER RESONANCE PARAMETERS.FOR THE SPIN OF  
*              L=0,RESONANCES HAVE BEEN RANDOMLY ASSIGNED BY THE  
*              COMPUTER CODE RNDSPIN (H. GRUPPELAAR)              
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
*   15-DEC-91: ISOTOPE MASS CORRECTED (H. TELLIER)                
******************************************************************
                                                                  
             CNEN      EVAL JUN76      CNEN-CDC-BOLOGNA           
                                                                  
    CERIUM-141           NEUTRON CROSS SECTION EVALUATION         
                                                                  
  -----------------------------MF 1-------------------------------
                                                                  
      MT 451                                                      
  2200 M/SEC CAPTURE 32.7B                                        
  RESONANCE INTEGRAL 165B                                         
                                                                  
  -----------------------------MF 2------------------------------ 
                                                                  
      MT 151                                                      
  CONTAINS RESOLVED PLUS UNRESOLVED MEAN PARAMETERS               
                                                                  
  -----------------------------MF 3-------------------------------
                                                                  
      MT 1,2 AND 102                                              
  A 1/V BACKGROUND IS GIVEN                                       
                                                                  
      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                                                       
  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                                                       
  EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND            
  T = CONSTANT FOR THE 2ND 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                
                                                                  
  COMPLETED  ON MONDAY 28 JUNE 1976 AT 12.39.50                   
                                                                  
 ***************** PROGRAM LINEAR (VERSION 83-1) *****************
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.100 PER-CENT      
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