2017 Fall Meeting

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Oral presentation

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

[2G10-13] Analysis Method Development 2

Thu. Sep 14, 2017 2:45 PM - 3:50 PM Room G (C213 - C Block)

Chair:Tomoaki Watanabe (JAEA)

3:00 PM - 3:15 PM

[2G11] Research on a neutron transport calculation method based on IGA

*Willem Van Rooijen1, Riho Horita1 (1. Research Institute of Nuclear Engineering)

Keywords:IGA method, Finite Element Method, Neutron transport theory, Numerical analysis, Arbitrary geometry

The IGA method is one of the Finite Element Methods, which can treat differential equations defined on arbitrary geometries. We are targeting the development of a calculation method to perform reactor physical analysis on arbitrary geometries.