Covariances in the ENDF/B-VII.1 Evaluated Nuclear Data Library

Covariance data in ENDF/B-VI.8 (47 materials), ENDF/B-VII.0 (26 materials), ENDF/B-VII.1 (190 materials), JEFF-3.1 (37 materials) and JENDL-3.3 (20 materials) were processed using the ERRORR module in NJOY-99.368. Processing was performed on NNDC's Linux Cluster using the 44- and 187-group energy structures and the constant-flux weighting function. To minimize the volume of plots for ENDF/B-VII.1's cross section covariances, only the most important reaction channels were included namely (n,total), (n,elastic), (n,inelastic), (n,2n), (n,fission), and (n,gamma).

The table below presents the plots (in Acrobat format) for each library. Please note that a shaded cell (in yellow) indicates that the material in the pertinent library does not contain covariance data.

Covariance data was also processed using NJOY 2010 in January 2012 at LANL and can be found here.

     *  Material could not be successfully processed.

    **  The 187-group energy structure is too detailed for this material.

   ***  MF34 could not be successfully processed.

  ****  MF31 could not be successfully processed.

*  Typo in Atlas: Correct absolute uncertainty is + 3000 b rather than + 300 b.