2018 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 305-1 Computational Science and Engineering

[3H10-13] Fuel and Reactor Analysis

Fri. Sep 7, 2018 2:45 PM - 3:50 PM Room H (B32 -B Building)

Chair:Takeshi Mitsuyasu(HGNE)

3:15 PM - 3:30 PM

[3H12] Investigation of neutron transport calculation using Iso-Geometric (IGA) method

(1)2 dimensional analysis

*Riho Horita1, W.F.G. van Rooijen2 (1. Univ. of Fukui, 2. Research Institute of Nuclear Engineering)

Keywords:Isogeometric Analysis method, finite element method, neutron transport theory, numerical analysis, arbitrary shape

We are developing a calculation method to analyze the neutron flux distribution for arbitrary shape geometries using the IGA method. A comparison was made with the results of NEWT. In this work we present the results of two dimensional analysis.