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 48-Cd-114 UA,ANL, +  EVAL-AUG94 J.McCabe, A.B. Smith, +          
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 4849                               
-----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   :-   ENDF/B-VI rel.4 (DIST-APR95 REV3-AUG96) 
                                                                  
******************************************************************
                                                                  
 ENDF/B-VI MOD 4 Revision (R.Q. Wright, ORNL, V. McLane, NNDC,    
                 August, 1996)                                    
 .  Added file 1 comments                                         
 .  Unresolved resonance range scattering radius was changed to   
    6.19 fm in order to eliminate a discontinuity in the total    
    cross section at 100 keV.                                     
                                                                  
 **************************************************************** 
                                                                  
 ENDF/B-VI MOD 3 (J. McCabe, A.B. Smith, J.W. Whalen, ANL,        
                  August, 1994)                                   
                                                                  
    Comprehensive neutronic evaluated files for the naturally-    
 occurring isotopes of cadmium are deduced from the experimental  
 data and nuclear models. Particular attention is given to those  
 processes relevant to fuel-cycle and fisson-product applications.
 Some discrepancies with the previous evaluation are very large   
 (e.g., as much as 100%), and the differences have the potential  
 for a pronounced effect on applications usage.  The present files
 are comprehensive, including many important processes that are   
 not represented in the previous evaluation.  See Ref.1 for       
 complete documentation.                                          
   The resonance region evaluation was carried over from the      
 previous evaluation, see following.                              
                                                                  
 REFERENCE                                                        
 1. J. McCabe, A.B. Smith, J.W. Whalen, Report ANL/NDM-129 (1993) 
    Argonne National Laboratory.                                  
                                                                  
 **************************************************************** 
                                                                  
 ENDF/B-VI MOD 2 Revision (R.Q. Wright, ORNL, December 1991)      
    See ANS Transactions, volume 68, part A, page 468             
                                                                  
    The ENDF/B-V evaluation used the SLBW formalism in the        
 resolvedresonance range but did not have unresolved resonance    
 parameters.                                                      
                                                                  
 Resolved resonance range (1.0E-5 eV to 8.0 keV)                  
 -----------------------------------------------                  
    The MLBW formalism is used for this evaluation.  The highest  
 energy resonance included is 10088 eV.  The resolved resonance   
 parameters are taken from Ref. 1 and from table 6 of Ref. 2.     
 Upper limit of the resolved resonance range is 8000 eV.  This    
 evaluation has 40 s-wave and 45 p-wave resonances including 5    
 s-wave resonances above 8000 eV.  The bound level at -225 eV has 
 a gamma-n0 of 34.53 meV and gamma-gamma of 53.0 meV.  The bound  
 level accounts for about 43% of the thermal capture cross        
 section.  The elastic cross section at thermal is 4.461 barns.   
 Note that the value of the capture resonance integral given on   
 page 48-22 of Ref. 1 should read 13+/-2 barns (see ref. 4).      
                                                                  
 Unresolved resonance range (8.0 to 100 keV)                      
 -------------------------------------------                      
    The unresolved resonance range fit is based on the average    
 capture cross sections from Ref. 3.                              
    The unresolved resonance parameters are based on:             
            D0 = 235 eV, S0 = 0.64, S1 = 3.5, AND S2 = 1.0        
            D1 =  90 eV, SG0 = 2.26, SG1 = 7.78                   
                                                                  
 File 3:                                                          
 -------                                                          
    Total, elastic, and capture are set to zero in the resolved   
 and unresolved resonance ranges (1.0E-5 eV to 100 keV).          
                                                                  
 2200 m/s capture cross section, barns                            
   (from resonance parameters) =   0.336                          
                                                                  
 computed resonance integral   =   13.15                          
                                                                  
 REFERENCES                                                       
                                                                  
 1.  S.F. Mughabghab, M. Divadeenam, and N.E. Holden, Neutron     
     Cross Sections, vol 1A, Academic Press, New York (1981).     
 2.  Musgrove et al., Neutron-capture resonance parameters and    
     cross sections for the even-A isotopes of cadmium, J. of     
     Physics, part G 4 (5), 771 (1978).                           
 3.  Musgrove et al., 1978 Harwell Conf. on Neutron Physics and   
     Nucl. Data, table V, page 449. (1978).  Values are mult. by  
     a factor of 1.0187 (see Nucl.Sci.Eng. 82, p. 230).           
 4.  S.F. Mughabghab, Neutron Cross Sections, vol 1B, Academic    
     Press, New York (1984). See page D-2.                        
                                                                  
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