NEA Data Bank
Back

 58-Ce-142 NEA        RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE          
 JEF/DOC-30           DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5843                               
-----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=5842) AND TRANSLATED    *
*     TO ENDF/B-V FORMAT AT THE NEA DATA BANK .                  *
******************************************************************
*   16-FEB-85: DATA EXTENDED UP TO 20 MEV.                        
*   13-OCT-87: 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                            
*    1-NOV-90: ADDITIONAL COMMENTS INSERTED                       
******************************************************************
 **************************************************************** 
 *                                                              * 
 *   MODIFICATIONS FOR JEF-2       58-CE-142                    * 
 *                                                              * 
 **************************************************************** 
 *                                                              * 
 *   COOPERATION ECN-PETTEN AND NEA DATA BANK                   * 
 *   H.A.J. VAN DER KAMP - ECN                                  * 
 *   H.GRUPPELAAR        - ECN                                  * 
 *   I.FOREST            - NEADB                                * 
 *   C.NORDBORG          - NEADB                                * 
 *                                                              * 
 **************************************************************** 
 *   RESOLVED RESONANCE REGION:                                 * 
 **************************************************************** 
 *                                                              * 
 *   THE ORIGINAL JEF-1 EVALUATION HAS BEEN MAINTAINED.         * 
 *                                                              * 
 *   EL=10-5 EV, EH=4.880 KEV.                                  * 
 *                                                              * 
 **************************************************************** 
 *   THERMAL VALUES (2200M/S):                                  * 
 **************************************************************** 
 *                                                              * 
 *   CALCULATED VALUES:                                         * 
 *   MT=2    SIGMA              = 3.77000 B                     * 
 *   MT=102  SIGMA              = 0.90000 B                     * 
 *   MT=102  RESONANCE INTEGRAL = 1.01462 B                     * 
 *                                                              * 
 *   EXPERIMENTAL VALUES:                                       * 
 *   MT=2    SIGMA              = NOT AVAILABLE                 * 
 *   MT=102  SIGMA              = 0.95 +- 0.05 B                * 
 *   MT=102  RESONANCE INTEGRAL = 1.15 +- 0.05 B                * 
 *                                                              * 
 **************************************************************** 
 *   REFERENCES:                                                * 
 **************************************************************** 
 *                                                              * 
 *   MU81: MUGHABGHAB,S.F., M.DIVADEENAM, N.E.HOLDEN            * 
 *         NEUTRON CROSS SECTIONS VOLUME 1                      * 
 *         NEUTRON RESONANCE PARAMETERS AND THERMAL CROSS       * 
 *         SECTIONS, PART A, Z=1-60, ACADEMIC PRESS 1981        * 
 *                                                              * 
 **************************************************************** 
                                                                  
             CNEN      EVAL APR76      CNEN-CDC-BOLOGNA           
                                                                  
    CERIUM-142           NEUTRON CROSS SECTION EVALUATION         
                                                                  
  -----------------------------MF 1-------------------------------
                                                                  
      MT 451                                                      
  2200 M/SEC CAPTURE 0.9B                                         
  RESONANCE INTEGRAL 0.97B                                        
                                                                  
  -----------------------------MF 2------------------------------ 
                                                                  
      MT 151                                                      
  CONTAINS RESOLVED PLUS UNRESOLVED MEAN PARAMETERS               
                                                                  
  -----------------------------MF 3-------------------------------
                                                                  
      MT 1,2 AND 102                                              
 THE BACKGROUND INCLUDES A 1/V RANGE                              
      MT 251,252,253                                              
  COMPUTED BY SYSMF FROM CERBERO ANGULAR DISTRIBUTIONS.           
                                                                  
  -----------------------------MF 4-------------------------------
                                                                  
      MT 2                                                        
  TRANSFORMATION MATRIX COMPUTED BY SYSMF FROM AMSTER.            
  LEGENDRE EXPANSION COEFFICIENTS COMPUTED BY SYSMF FROM CERBERO  
                                                                  
      MT 16                                                       
  ASSUMED ISOTROPIC IN THE LABORATORY FRAME OF REFERENCE          
                                                                  
      MT 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                                                       
  EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND            
  T = CONSTANT FOR THE 2ND NEUTRON                                
                                                                  
      MT 17                                                       
  EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) AND            
  T = CONSTANT FOR THE 2ND AND THE 3RD 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 5 APRIL 1976 AT 15.46.29                   
                                                                  
 ***************** PROGRAM LINEAR (VERSION 83-1) *****************
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.100 PER-CENT      
Back