NEA Data Bank
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 27-Co- 58MNEA        RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP   
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 2723                               
-----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   ***********************
                                                                  
   Skeleton MF-5 MT-22,28 added                                   
                                                                  
   DATA TAKEN FROM   :-   JEF-2.2 (DIST-JAN92)                    
                                                                  
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*   JEF-2                                                        *
*     DATA WERE TAKEN FROM RCN-2.                                *
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*    6-SEP-84: COMPILATION ERROR IN TOTAL CORRECTED.             *
*    4-FEB-85: DATA WERE EXTENDED DOWN TO 1.0E-5 EV  AFTER        
*              CONSULTAION WITH H.GRUPPELAAR. NEW BACKGROUND      
*              DATA CALCULATED.                                   
*   21-FEB-85: Q-VALUE FOR MT=22,CORRECTED AND THRESHOLD ENERGY   
*              INSERTED,                                          
*              Q-VALUES FOR MT=28,102,103,107 CORRECTED           
*   14-OCT-87: FOR THE SPIN OF L=0,RESONANCES HAVE BEEN RANDOMLY  
               ASSIGNED BY THE COMPUTER CODE RNDSPIN (GRUPPELAAR) 
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                        COBALT- 58M                               
                                                                  
 AUTOMATICALLY TRANSLATED INTO ENDF/B FORMAT FROM KEDAK SOURCE BY 
                                                                  
                           K T O E - 3                            
                                                                  
ORIGINAL COMMENT IS:                                              
                                                                  
 RCN-2 EVL. FOR C0-58M (RUN N) BY H.GRUPPELAAR AND H.A.J.VAN DER K
 MINIMUM ENERGY                        .00100    EV               
 MIN EN OF STATISTICAL MODEL           .51000   KEV               
 ENERGY OF FIRST EXCITED STATE      -24.9       KEV               
 CONTINUOUS STAT MODEL ABOVE          1.21100   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 METASTABLE TARGET*********************************
 RESOLVED RESONANCE REGION UPTO ABOUT 0.5 KEV                     
      ONLY ONE RESONANCE GIVEN. THIS WAS FITTED TO OBTAIN         
       AGREEMENT WITH EXPERIMENTAL VALUES FOR THERMAL             
      CAPTURE CROSS SECTION (SIGMA= 136 KB )   (MU73)             
      THE CALCULATED RESONANCE INTEGRAL IS RI=180 KB, NOT FAR FROM
      THE VALUE MEASURED BY HALPERIN ET AL.(HA64).                
      POSSIBLY SIGMA ABSORBTION IN THE RESONANCE REGION           
      CONSISTS OF A CONTRIBUTION OF 75 PERCENT  FOR THE (N,GAMMA) 
      REACTION AND OF A CONTRIBUTION OF 25 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 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.   
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