NEA Data Bank
Back

 27-Co- 58 NEA        RCOM-JUN83 SCIENTIFIC CO-ORDINATING GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 2722                               
-----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   ***********************
                                                                  
   Skeleton MF-5 MT-22,28 added                                   
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
******************************************************************
                                                                  
******************************************************************
*   JEF-2                                                        *
*     DATA WERE TAKEN FROM RCN-2 EVALUATION.                     *
******************************************************************
*   23-AUG-84: COMMENT ADDED. Q-VALUE IN MF=3,MT=91 CORRECTED.    
*    4-FEB-85: DATA WERE EXTENDED DOWN TO 1.0E-5 EV AFTER         
*              CONSULTAION WITH H.GRUPPELAAR. NEW BACKGROUND      
*              CROSS SECTION CALCULATED.                          
*   21-FEB-85: Q-VALUES FOR MT=102 AND 103 CORRECTED              
*              Q-VALUE FOR MT=22,107 CORRECTED AND CORRESPONDING  
*              THRESHOLD ENERGY POINT INSERTED                    
*   14-OCT-87:  FOR THE SPIN OF L=0 RESONANCES HAVE BEEN RANDOMLY 
                ASSIGNED BY THE COMPUTER CODE RNDSPIN (GRUPPELAAR)
******************************************************************
                                                                  
                        COBALT-58                                 
                                                                  
 AUTOMATICALLY TRANSLATED INTO ENDF/B FORMAT FROM KEDAK SOURCE BY 
                                                                  
                           K T O E - 3                            
                                                                  
ORIGINAL COMMENT IS:                                              
                                                                  
 RCN-2 EVL. FOR CO-58G BY H.GRUPPELAAR AND H.A.J.VAN DER KAMP (29/
 MINIMUM ENERGY                        .00100    EV               
 MIN EN OF STATISTICAL MODEL           .60000   KEV               
 ENERGY OF FIRST EXCITED STATE       24.90000   KEV               
 CONTINUOUS STAT MODEL ABOVE          1.23600   MEV               
 HIGH ENERGY MODEL ABOVE              6.50000   MEV               
 MAXIMUM ENERGY                      20.00000   MEV               
 LEVEL DENSITY PARAMETER  CO058       6.50000 1/MEV               
 LEVEL DENSITY PARAMETER  CO057       6.00000 1/MEV               
 *****CROSS SECTIONS FOR NUCLIDES IN COOLING CIRCUIT OF LMFBR*****
 *****COBALT-58 GROUND STATE TARGET*******************************
 RESOLVED RESONANCE REGION UPTO ABOUT 0.5 KEV                     
      ONLY ONE RESONANCE GIVEN. THIS WAS FITTED TO OBTAIN         
      REASONABLE AGREEMENT WITH EXPERIMENTAL VALUES FOR THERMAL   
      CAPTURE CROSS SECTION (SIGMA= 1880 B.) AND RESONANCE        
      INTEGRAL( RI= 6890 B.), VALUES GIVEN IN BNL-325             
      POSSIBLY SIGMA ABSORBTION IN THE RESONANCE REGION           
      CONSISTS OF A CONTRIBUTION 0F 10 PERCENT FOR THE (N,GAMMA)  
      REACTION AND A CONTRIBUTION OF 90 PERCENT FOR THE (N,P)     
      REACTION.                                                   
 OPTICAL MODEL AND STATISTICAL MODELS ABOVE 0.5 KEV               
      TOTAL, CAPTURE AND NEUTRON SCATTERING CROSS SECTIONS WITH   
      CODE SASSI-ECN.                                             
      NEUTRON OPTICAL MODEL FROM FORT (FO79).                     
      DOBS=1.17 KEV FROM SYSTEMATICS.                             
      GUESSED AVERAGE CAPTURE WIDTH= 0.5 EV.                      
      CHARGED-PARTICLE EMISSION CROSS SECTIONS FROM CODES CERBERO 
      AND ERINNI.                                                 
      THE (N,D) CROSS SECTION CALCULATED WITH CODE THRES-2        
      WITH RENORMALIZATION TO SYSTEMATICS.                        
      (N,P) CROSS SECTION IS IMPORTANT DOWN TO THERMAL            
      ENERGIES.                                                   
      LEVEL-DENSITY PARAMETERS MOSTLY FROM SYSTEMATICS.           
      LEVEL SCHEMES FROM NUCLEAR DATA SHEETS AND OWN EVALUATION.  
      NO EXPERIMENTAL CROSS SECTIONS AVAILABLE FOR COMPARISONS.   
Back