NEA Data Bank
Back

 54-Xe-130 NEA        RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5443                               
-----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 ENDF/B-V(MAT=1350).                   *
******************************************************************
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
******************************************************************
           BNL        EVAL-MAR78 M.R.BHAT AND S.F.MUGHABGHAB      
                      DIST-APR79 REV0-MAR78            780412     
           THIS EVALUATION IS THE SAME AS IN ENDF/B-IV(MAT=1174)  
           EXCEPT FOR CHANGES IN THE FOLLOWING MF/MTS - 2/151,    
           3/1,3/2,3/102,5/17                                     
 DATA USED                                                        
 2200 M/SEC CAPTURE CROSS SECTION 6.2B. THIS WAS OBTAINED BY      
            TAKING  0.42B FOR THE CROSS-SECTION TO THE METASTABLE 
            STATE WHICH IS A MEAN OF 0.495B BY E.KONDAIAH ET.AL.  
            NPA120,329,1968 AND 0.34B BY R.S.TILBURY ET.AL. NSE31,
            545,1968 AND USING 13.83 FOR THE RATIO OF THE CROSS-  
            SECTIONS TO THE GROUND AND METASTABLE STATES. THIS IS 
            A VALUE GOT BY KONDAIAH ET.AL. FOR XE132.             
 RESOLVED RESONANCE PARAMETERS BY P.RIBON,THESIS,UNIVERSITY OF    
           PARIS,JAN16,1969.BOUND LEVEL PARAMETERS ADJUSTED TO    
           GIVE THE ASSIGNED THERMAL CAPTURE CROSS-SECTION.       
 MEV TOTAL CROSS SECTION OF NATURAL XENON BY F.J.VAUGHN ET.AL.    
           PHYS.REV.118,683,1960                                  
 (N,P) CROSS SECTION NORMALIZED TO A VALUE OF 6.7+-0.8MB AT14.4MEV
        AS MEASURED BY E.KONDAIAH ET.AL. NP A120,337,1968         
           THE NEW DATUM BY SIGG ET.AL. AT 14.6MEV IS HIGHER BY   
           ABOUT 66PER-CENT AND ACANNOT BE RECONCILED WITH THE    
           OLDER MEASUREMENT.                                     
 PARTICLE THRESHOLD ENERGIES CALCULATED USING THE DATA OF         
           A.H.WAPSTRA AND N.B.GOVE,NUCLEAR DATA TABLES VOL9A,267,
           1971                                                   
 NUCLEAR MODEL CALCULATIONS                                       
 OPTICAL MODEL PARAMETERS WILMORE-HODGSON PARAMETERS P.E.HODGSON  
           ANN.REV.NUCL.SCI.VOL17,1,1967 R0=1.26FM.               
 CODES USED                                                       
           1.ABACUS-2 E.H.AUERBACH BNL6562,1964                   
            TOTAL AND SHAPE-ELASTIC CROSS-SECTIONS                
           2.COMMNUC(AI-AEC-12931)C.DUNFORD. COMPOUND NUCLEUS     
            REACTION CROSS SECTIONS.                              
           3.FASCRO(TO BE PUBLISHED)S.PEARLSTEIN,(N,PARTICLE)CROSS
            SECTIONS.                                             
           4.CHAD(NAA-SR-11231)R.F.BERLAND. ANGULAR DISTRIBUTION  
            DATA FITTED BY USING THIS CODE.                       
 NUCLEAR TEMPERATURE CALCULATIONS BASED ON GILBERT AND CAMERON    
 CAN.JOUR.PHYS.VOL43,1446,1965                                    
Back