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 48-Cd-112 UA,ANL, +  EVAL-AUG94 J.McCabe, A.B. Smith, +          
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 4843                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
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**         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)                                   
   File 1 comments added                                          
   File 3, MT=4 Obsolete code deleted                             
                                                                  
 **************************************************************** 
                                                                  
 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        
 resolved resonance range and did not have unresolved resonance   
 parameters.                                                      
                                                                  
 Resolved resonance range (1.0E-5 eV to 7.35 keV)                 
 ------------------------------------------------                 
   The MLBW formalism is used for this evaluation.  The highest   
 energy resonance included is 11455 eV.  The resolved resonance   
 parameters are taken from ref. 1 and from table 5 of ref. 2.     
 Upper limit of the resolved resonance range is 7350 eV.  This    
 evaluation has 64 s-wave and 54 p-wave resonances including 24   
 s-wave resonances above 7350 eV.  The bound level at -125 eV has 
 a gamma-n0 of 93.91 meV and gamma-gamma of 83 meV (ref. 1).  The 
 bound level accounts for about 95% of the thermal capture cross  
 section.  The elastic cross section at thermal is 6.31 barns.    
                                                                  
 Unresolved resonance range (7.35 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 = 190 eV, S0 = 0.5, S1 = 4.4, AND S2 = 1.5         
            D1 =  75 eV, SG0 = 4.05, SG1 = 12.0                   
                                                                  
 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) =   2.195                          
                                                                  
 computed resonance integral   =   13.50                          
                                                                  
 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 1.0069 (see Nucl.Sci.Eng. 82, p. 230).           
                                                                  
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