Comparison of ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF 3.3 Nuclear Data Libraries on Criticality Calculation Using WIMS/CITVAP Code

Document Type : Original Article

Authors

1 Reactors Department, Nuclear Research Center, Egyptian Atomic Energy Authority, Egypt.

2 Egyptian Nuclear & Radilogical Regulatory Authority

3 Reactors department, Egyptian Atomic Energy Authority

Abstract

This paper presents the work carried out during the first year of the research contract No. 24284 titled “accuracy evaluation of available fission yield data and updating” under the umbrella of the Coordinated Research Project (CRP): “updating fission yield data for applications” organized by the International Atomic Energy Agency (IAEA) with the main objective of updating the evaluated independent and cumulative fission yield data for U-235, U-238, and Cf-252. In this research, the latest ENDF/B-VIII.0 and JEFF3.3 data libraries that were released in 2018 and 2017, respectively, as well as the ENDF/B-VII.1 data library, were tested on the ETRR-2 using WIMS-5B/CITVAP computational codes. Since the reactor criticality calculations are very sensitive to the accuracy of the data libraries, criticality benchmarks were selected in the work for the evaluation of these libraries.
The results showed that the JEFF3.3 library has better agreement with the measurements than the ENDF/B-VIII.0 library. But the ENDF/B-VIII.0 library result is within the accepted range.

Keywords

Files

Share

How to cite

Statistics