Processing ENDF/B-V uncertainty data into multigroup covariance matrices

Date Issued
March 1, 1980
Author(s)
Smith, James D.
Advisor(s)
H. L. Dodds
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Abstract
The purpose of this work is to develop and demonstrate the capability of processing Evaluated Nuclear Data File, system B, version five (ENDF/B-V) uncertainty data into multigroup covariance matrices. These covariances may then be folded with sensitivity coefficients to obtain uncertainties in selected integral parameters such as K-effective and breeding ratio.

The project consisted of separating the previous uncertainty processor (PUFF) from the basic nuclear data cross section processor (MINX), updating the uncertainty processor to the ENDF/B-V format, programming the processor for new uncertainty data, and demonstrating the processor capabilities by producing a multigroup covariance library. These capabilities were verified in various ways including hand calculations and comparisons with other known results.

A computer code named PUFF-II was written to perform the task described above. The code is capable of processing all uncertainty data currently entered in ENDF/B-V. The only limitation of the code is the treatment of uncertainties in resonance data.

Major
Nuclear Engineering
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