Presentation Information

[2D06]Comparison of ENDF/B-VIII.0 and ENDF/B-VIII.1 by BWR sub-assembly depletion calculations

*Shinichi Namizono1, Tojo Masayuki1, Kaneko Hirohisa1 (1. GNF-J)

Keywords:

Boiling water reactor,Depletion calculation,Monte Carlo method,Nuclear data

The latest release of the ENDF/B nuclear data, ENDF/B-VIII.1, contains updates for many isotopes, and the influence of those updates on BWR depletion calculations must be assessed. In this research we use the Monte Carlo code MCNP-6.3.1 to investigate the influence of the updates from ENDF/B-VIII.0 to ENDF/B-VIII.1 for individual isotopes.