2016 Annual Meeting

Presentation information

Oral Presentation

III. Fission Energy Engineering » 301-1. Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2O10-12] nuclear data development

Sun. Mar 27, 2016 2:45 PM - 3:35 PM Room O (Lecture Rooms C C201)

Chair: Kenichi Tada (JAEA)

2:45 PM - 3:00 PM

[2O10] Generation of multi-group cross sections and covariance data based on JENDL-4 for the SCALE code system

*Willem van Rooijen1 (1.Research Institute of Nuclear Engineering, University of Fukui)

Keywords:Multi-group cross sections, Covariance data, SCALE, JENDL-4, AMPX

For the SCALE code system we have created a multi-group cross section library (AMPX format) and corresponding covariance data (COVERX format) using the JENDL-4 evaluated nuclear data. Calculations indicate a satisfactory performance of the library. Validation calculations are being performed.