NEA Data Bank
Back

 47-Ag-109 NEA        RCOM-JUL83 H.GRUPPELAAR,E.MENAPACE          
 JEF/DOC-30           DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 4731                               
-----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 RCN-3 EVALUATION (MAT=4709).          *
******************************************************************
*   16-FEB-85: NEW BACKGROUND CROSS SECT. CALCULATED AND INSERTED 
*    6-MAR-85: Q-VALUES FOR MT=102,103,107 CORRECTED              
*   30-SEP-86: RESONANCE PARAMETER SECTION UPDATED USING DATA    *
*              FROM THE 4TH ED. OF BNL-325.                      *
*   27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED   
*              FROM REAC-ECN-4 LIBRARY                            
*    1-NOV-90: ADDITIONAL COMMENTS INSERTED                       
******************************************************************
 **************************************************************** 
 *                                                              * 
 *   MODIFICATIONS FOR JEF-2       47-AG-109                    * 
 *                                                              * 
 **************************************************************** 
 *                                                              * 
 *   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:                                 * 
 **************************************************************** 
 *                                                              * 
 *   RESOLVED RESONANCE PARAMETERS WERE REPLACED BY DATA FROM   * 
 *   MOST RECENT BROOKHAVEN COMPILATION(MU81).                  * 
 *                                                              * 
 *   EL=10-5 EV, EH=0.984 KEV.                                  * 
 *                                                              * 
 **************************************************************** 
 *   THERMAL VALUES (2200M/S):                                  * 
 **************************************************************** 
 *                                                              * 
 *   CALCULATED VALUES:                                         * 
 *   MT=2    SIGMA              =    2.29851 B                  * 
 *   MT=102  SIGMA              =   90.7101  B                  * 
 *   MT=102  RESONANCE INTEGRAL = 146.762    B                  * 
 *                                                              * 
     EXPERIMENTAL VALUES:                                       * 
 *   MT=2    SIGMA              =  2.55 +- 0.06 B               * 
 *   MT=102  SIGMA              = 91.0  +- 1.0  B               * 
 *   MT=102  RESONANCE INTEGRAL = NOT AVAILABLE                 * 
 *                                                              * 
 **************************************************************** 
 *   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        * 
 *                                                              * 
 **************************************************************** 
                                                                  
      ORIGINAL DATA IN KEDAK FORMAT WERE TRANSLATED INTO ENDF/B   
      FORMAT WITH KTOE-3.                                         
                                                                  
******************************************************************
                                                                  
    EVAL. FOR:      SILVER       -   109        DISTR:   JUL  80  
                                                                  
ORIGINAL COMMENT IS:                                              
                                                                  
$RCN 3 EVALUATION H.GRUPPELAAR         AG109Z     27/01/78  $     
 (N,ALPHA) AND (N,P) ADDED                                    REV 
 MINIMUM ENERGY                        .00100    EV               
 MIN EN OF STATISTICAL MODEL           .98424   KEV               
 ENERGY OF FIRST EXCITED STATE       88.00000   KEV               
 CONTINUOUS STAT MODEL ABOVE           .91230   MEV               
 HIGH ENERGY MODEL ABOVE              6.50000   MEV               
 MAXIMUM ENERGY                      15.00000   MEV               
 LEVEL DENSITY PARAMETER  AG109      17.80000 1/MEV               
 LEVEL DENSITY PARAMETER  AG108      17.15000 1/MEV               
 RESOLVED RESONANCE REGION UPTO 976.1 EV                          
 ******ADJUSTED EVALUATION BASED ON STEK AND CFRMF INTEGRAL DATA**
       EVALUATION WITH SIGMA-2 AT O K, MULTILEVEL FORMULA         
       RESOLVED RESONANCES AS COMPILED BY RIBON ET AL. (RI75), WIT
       A VALUE OF 129 MV FOR THE CAPTURE WIDTH OF RESONANCES FOR  
       WHICH THIS QUANTITY IS NOT KNOWN                           
 STRENGTH FUNCTION REGION UPTO 100 KEV                            
       CAPTURE CROSS SECTIONS WITH CODE FISPRO-RCN                
       OTHER CROSS SECTIONS WITH CODE SASSI-RCN                   
       S-WAVE STRENGTH FUNCTION, S0=0.64                          
       P-WAVE STRENGTH FUNCTION, S1=3.95                          
       OTHER STRENGTH FUNCTIONS FROM OPTICAL MODEL (MO63A)        
       DOBS=16.3 EV                                               
       GAMMA WIDTH= 132 MV                                        
 HIGH ENERGY REGION                                               
       ALL CROSS SECTIONS WITH CODE SASSI-RCN                     
       OPTICAL MODEL FROM MOLDAUER(MO63A)                         
       LEVEL SCHEME OF TARGET NUCLEUS FROM EL-BEWEDI ET AL.(EL75) 
       REVISIONS IN MOST XSECT. ABOVE 1.5 MEV TO FIT NATURAL AG DA
 ***************** PROGRAM LINEAR (VERSION 83-1) *****************
 DATA LINEARIZED TO WITHIN AN ACCURACY OF     0.100 PER-CENT      
Back