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 54-Xe-129 NEA        RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5440                               
-----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)                    
                                                                  
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*   JEF-2                                                        *
*     DATA WERE TAKEN FROM ENDF/B-V(MAT=1349).                   *
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*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
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           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=1173)  
           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 18+-7B. THIS IS ESSENTIALLY DUE 
           TO T.A.EASTWOOD AND F.BROWN EANDC(CAN)-16,6,1963,WITH  
           3B DEDUCTED TO ALLOW FOR THE FACT THAT THE VALUE GIVEN 
           BY THEM IS FOR THE EFFECTIVE CROSS SECTION.            
 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.    
           PHY.REV.118,683,1960.                                  
 PARTICLE THRESHOLD ENERGIES CALCULATED USING THE DATA OF         
           A.H.WAPSTRA AND N.B.GOVE,NUCLEAR DATA TABLES VOLA9,267,
           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                                    
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