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 54-Xe-135 NEA        RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 5458                               
-----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=1294).                   *
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*   26-NOV-84: RADIOACTIVE DECAY DATA DELETED.                    
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
*    1-NOV-90: ADDITIONAL COMMENTS INSERTED                       
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 **************************************************************** 
 *                                                              * 
 *   MODIFICATIONS FOR JEF-2       54-XE-135                    * 
 *                                                              * 
 **************************************************************** 
 *                                                              * 
 *   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          * 
 *   MOST RECENT BROOKHAVEN COMPILATION(MU81).                  * 
 *                                                              * 
 *   EL=10-5 EV, EH=100.0 KEV.                                  * 
 *                                                              * 
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 *   THERMAL VALUES (2200M/S):                                  * 
 **************************************************************** 
 *                                                              * 
 *   CALCULATED VALUES:                                         * 
 *   MT=2    SIGMA              =  295686.0  B                  * 
 *   MT=102  SIGMA              = 2636300.0  B                  * 
 *   MT=102  RESONANCE INTEGRAL =    7639.79 B                  * 
 *                                                              * 
 *   EXPERIMENTAL VALUES:                                       * 
 *   MT=2    SIGMA              = NOT AVAILABLE                 * 
 *   MT=102  SIGMA              = 2650000 +- 110000 B           * 
 *   MT=102  RESONANCE INTEGRAL = NOT AVAILABLE                 * 
 *                                                              * 
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 *   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        * 
 *                                                              * 
 **************************************************************** 
                                                                  
           BNW        EVAL-JUN67 B.R.LEONARD,JR. AND K.B.STEWART  
 PRI.COM.JUNE,1967    DIST-APR79 REV1-MAY75            781218     
 *         *          *          *         *          *         * 
 ENDF/B VERSION-IV MODIFICATIONS=                  (APR74)        
 FILE EXTENDED FROM 1.0 KEV TO 20.0 MEV BY F.SCHMITTROTH AND      
 R.E. SCHENTER (HEDL)                                             
 ADDED SAME ANGULAR DISTRIBUTION (MF=4,MT=2) AS FOR               
 CS-133 (MAT=1141).                                               
 *          *         *          *         *          *         * 
 DATA MODIFIED JUNE,1970 TO CONFORM TO ENDF/B-II FORMATS          
 *         *          *          *         *          *         * 
 XENON-135 ENTRY BY B.R.LEONARD,JR. AND K.B.STEWART REF.1         
           JUNE 1967                                              
*          *          *          *          *          *          
     XE 135  EVALUATION UPDATED FOR ENERGIES FROM  1  KEV TO      
     20  MEV.                                                     
     F. SCHMITTROTH AND R.E. SCHENTER                             
     WESTINGHOUSE HANFORD COMPANY  (FEBRUARY 1974)                
         MT=1  TOTAL CROSS SECTION WAS OBTAINED FROM MOLDAUERS    
               OPTICAL POTENTIAL,REF.6.                           
         MT=2  ELASTIC CROSS SECTION WAS OBTAINED BY SUBTRACTING  
               THE INELASTIC AND CAPTURE CROSS SECTIONS FROM      
               TOTAL.                                             
         MT=4,51,91   INELASTIC CROSS SECTIONS WERE OBTAINED      
               FROM THE COMPOUND NUCLEUS CODE COMNUC,REF.7.       
         MT=102   NEUTRON CAPTURE OBTAINED FROM THE CODE NCAP,    
               REF.8.                                             
*          *          *          *          *          *          
 MF=1                     GENERAL INFORMATION                     
   MT=451 ATOMIC MASS = 134.907 REF.2                             
 MF=3                     SMOOTH CROSS SECTIONS                   
   MT=1   THE RESONANCE PARAMETERS OF SUMNER(REF.4) HAVE BEEN     
   MT=2    ACCEPTED AS THE BEST ESTIMATE OF THE CROSS SECTION.    
   MT=102  THESE PARAMETERS HAVE BEEN USED IN THE PROGRAM         
           UNICORN(REF.5) TO CALCULATE POINT VALUES AT 0 DEG.K    
           FROM 0.0001 EV TO 1 KEV .THE CALCULATIONS GIVE         
           SIGMA CAPTURE = 2.636E+06 BARNS AT 0.0253 EV.          
Q-VALUE REF.J.MATTAUCH ET AL.NUC.PHYS 67(1965)NO.1                
                          REFERENCES                              
  1. LEONARD,B.R.,STEWART,K.B.,PNL JUNE 1967                      
  2. EVERLING,F.,ET.AL.,NUCL.PHYS.18,529(1960).                   
  4. SUMNER,H.M.,AEEW-R-116(JUNE 1962).                           
  5. OTTER,J.M.,NAA-SR.11980,VOL.6(JUNE 1966).                    
  6. P.A.MOLDAUER,PHYS.REV.,VOL.135(1964)B642.                    
  7. C.DUNFORD, COMNUC-3,PRIVATE COMM. TO A.PRINCE.               
  8. F.SCHMITTROTH,HEDL-TME-71-106,AUGUST 1971.                   
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