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 48-Cd-108 UA,ANL,+   EVAL-AUG94 J.McCabe, A.B. Smith, +          
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 4831                               
-----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                                          
                                                                  
 **************************************************************** 
                                                                  
 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, October 1991)       
    See ANS Transactions, volume 68, part A, page 468.            
                                                                  
    The ENDF/B-V evaluation did not have resolved resonance       
 parameters or an unresolved range.                               
                                                                  
 Resolved resonance range (1.0E-5 eV to 6.1 keV)                  
 -----------------------------------------------                  
    The MLBW formalism is used for this evaluation.  The highest  
 energy resonance included is 5970 eV.  The resolved resonance    
 parameters are taken from ref. 1 and from table 3 of ref. 2.     
 In ref. 1 there is a gap between about 500 and 2500 eV where no  
 resolved resonance data is available.  18 fictitious s-wave res- 
 onances were inserted, starting at 590 eV and ending at 2480 eV. 
 Above 2500 eV, 31 resonances were assigned as s-wave and 29 were 
 were assigned as p-wave.  For the s-wave resonances the average  
 gamma width is 0.1055 eV; the average level spacing is 119.6 eV; 
 The s-wave strength function is 1.446E-4.  The p-wave capture    
 width is set to 0.125 eV for all 29 resonances.                  
                                                                  
 Unresolved resonance range (6.1 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 = 100 eV, S0 = 1.44, S1 = 4.4, AND S2 = 0.5        
            D1 = 46.67 eV, SG0 = 10.5, SG1 = 25.71                
                                                                  
 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) =    1.10                          
                                                                  
 computed resonance integral   =   16.98                          
                                                                  
 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 0.985 (see Nucl.Sci.Eng. 82, p. 230).            
                                                                  
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