NEA Data Bank
Back

 48-Cd-106 UA,ANL,+   EVAL-AUG94 J.McCabe, A.B. Smith, +          
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 4825                               
-----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   ***********************
                                                                  
   DATA TAKEN FROM   :-   ENDF/B-VI rel.4 (DIST-APR94 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, December, 1991)     
    See ANS Transactions, volume 68, part A, page 468.            
                                                                  
    The previous evaluation carried over from ENDF/B-V, did not   
 have resolved resonance parameters or an unresolved resonance    
 range.                                                           
                                                                  
 Resolved resonance range (1.0e-5 ev to 6.0 kev)                  
 -----------------------------------------------                  
    The MLBW formalism is used for this evaluation.  The highest  
 energy resonance included is 5881 eV.  The resolved resonance    
 parameters are taken from Ref. 1 and from table 2 of Ref. 2.     
 In Ref. 1 there is a gap between about 700 and 2500 eV where no  
 resolved resonance data is available.  14 fictitious s-wave res- 
 onances were inserted, starting at 755 eV and ending at 2497 eV. 
 Above 2500 eV, 25 resonances were assigned as s-wave and 27 were 
 were assigned as p-wave.  Also 4 fictitious s-wave resonances    
 were inserted above 6 keV.  For s-wave resonances the average    
 gamma width is 0.1612 eV; the average level spacing is 142.6 eV; 
 The s-wave strength function is 0.834E-4.  The p-wave capture    
 width is set to 0.175 eV for all 27 resonances.                  
                                                                  
 Unresolved resonance range (6.0 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 = 110 eV, S0 = 1.0, S1 = 5.0, AND S2 = 0.5         
            D1 =  42 eV, SG0 = 14.09, SG1 = 41.67                 
                                                                  
 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                                   
   (from resonance parameters) =    1.12 barns                    
                                                                  
 Computed resonance integral   =   14.20 barns                    
                                                                  
 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).            
                                                                  
Back