2016 Annual Meeting

Presentation information

Oral Presentation

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

[1O17-21] uncertainty quantification 2

Sat. Mar 26, 2016 4:55 PM - 6:15 PM Room O (Lecture Rooms C C201)

Chair: Kazuki Kirimura (MHI)

5:10 PM - 5:25 PM

[1O18] Uncertainty Quantification of Neutron Flux Due to Cross Section Data in Neutron Shielding Calculation

*KIMIHIRO YOKOI1, TOMOHIRO ENDO2, AKIO YAMAMOTO2, YOSHIO KIMURA3, RYOJI MIZUNO3 (1.Nagoya University Division of Quantum Science and Energy Engineering, 2.Nagoya University Department of Materials,Physics and Energy Enginering, 3.Chuden CTI Analyzing and Engineering Solutions Department, IT Solutions Division)

Keywords:Neutron shielding calculation, Random sampling method, Uncertainty quantification, Decommissioning

ランダムサンプリング法を用いて、遮蔽計算における断面積起因の中性子束の不確かさを評価した。1次元体系を対象としたTRANSX/ANISNによる中性子束の不確かさ評価結果について報告する。