JOPSS:検索結果一覧

検索結果：　3 件中 1件目～3件目を表示

発表形式

Initialising ...

選択項目を絞り込む

掲載資料名

Initialising ...

発表会議名

Initialising ...

筆頭著者名

Initialising ...

キーワード

Initialising ...

使用言語

Initialising ...

発行年

Initialising ...

開催年

Initialising ...

論文

The Development of Petri Net-based continuous Markov Chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component interdependency under longtermly thereat

Li, C.-Y.; 渡部晃*; 内堀昭寛; 岡野靖

Journal of Nuclear Science and Technology, 23 Pages, 2023/00

https://doi.org/10.1080/00223131.2023.2290067

被引用回数：1 パーセンタイル：68.31(Nuclear Science & Technology)

For all the nuclear reactor systems, quantitative assessment of the accident management (AM) effects against long-term external hazards became one of the essential issues after the lesson learned from the Fukushima Daiichi Nuclear Power Plant accident. However, the influence from the safety systems' stochastic and dynamic shifting between multiple working states, which is related to the interaction with the adjacent components/systems in general, has not been accounted for yet. Therefore, this research aims to develop a dynamic probability risk assessment tool considering repairable multi-component interdependency for investigating the AM influences on the multi-state safety systems under long-term external hazards. Based on the newly proposed methodology in this research via integrating the Petri Net (PN) model with the continuous Markov chain Monte Carlo (CMMC) method, a framework applying PN-CMMC methodology to a severe accident analysis code, SPECTRA, had been originally constructed. Different AM influences on the multi-state decay heat removal systems against long-term volcanic ashfall were also quantitatively confirmed, indicating that halving the repairing time is more influential in suppressing the core damage frequency than doubling the number of adjacent electricity support systems. Therefore, the PN-CMMC-SPECTRA framework can further assess the uncharted dynamic multi-state concerns, leading to a safer AM strategy.

論文

Safety enhancement approach against external hazard on JSFR reactor building

山本智彦; 加藤篤志; 近澤佳隆; 原裕之*

Nuclear Technology, 206(12), p.1875 - 1890, 2020/12

https://doi.org/10.1080/00295450.2020.1726155

被引用回数：0 パーセンタイル：0.01(Nuclear Science & Technology)

福島第一原子力発電所の事故を受けて、2010年までに設計されたJSFR建屋に対する地震や津波等の外部事象に対しての評価と対策案について報告する。

論文

Development of risk assessment methodology of decay heat removal function against external hazards for sodium-cooled fast reactors, 1; Project overview and margin assessment methodology against snow

山野秀将; 西野裕之; 栗坂健一; 岡野靖; 堺公明; 山元孝広*; 石塚吉浩*; 下司信夫*; 古川竜太*; 七山太*; et al.

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 10 Pages, 2015/05

本論文では、プロジェクト概要に加えて、主に積雪マージン評価手法開発について述べる。積雪マージン評価には降雪速度と継続時間の組み合わせが指標となる。降雪中は除雪が期待できるから、除雪速度が降雪速度を下回ったときに除熱失敗と定義すると、その除熱失敗に至るまでの降雪継続時間がマージンとみなされるという積雪マージン評価手法を開発した。