更新情報
第17回
リスク情報を活用した保全の合理化に向けた定量的なリスク評価の 必要性を判定する簡易スクリーニング手法の提案
著者:
橋立 竜太,矢田 浩基,高屋 茂,二神 敏,山野 秀将,栗坂 健一,江沼 康弘,(JAEA)
発刊日:
公開日:
キーワードタグ:
Fast Reactor Laundry System Maintenance Rationalization Probabilistic Risk Assessment System Based Code
橋立 竜太,矢田 浩基,高屋 茂,二神 敏,山野 秀将,栗坂 健一,江沼 康弘,(JAEA)
発刊日:
公開日:
キーワードタグ:
Fast Reactor Laundry System Maintenance Rationalization Probabilistic Risk Assessment System Based Code
If components can be maintained according to a target reliability of nuclear power plants, plant safety and economic efficiency could be improved by avoiding excessive or insufficient margins. This approach can rationalize the maintenance of low target reliability components and concentrate resources (people, money, and time) on the maintenance of high target reliability components. It would take a long time to evaluate the target reliability for all components in the plant by quantitatively using probabili...
英字タイトル:
Proposal of a Simple Screening Method Which Determines Necessity of Quantitative Risk Assessment for Maintenance Rationalization Using Risk Information
英字タイトル:
Proposal of a Simple Screening Method Which Determines Necessity of Quantitative Risk Assessment for Maintenance Rationalization Using Risk Information
第17回
原子炉構造レジリエンスの可視化手法
著者:
桑原 悠士,出町 和之,笠原 直人,陳 実,(東京大),西野 裕之,小野田 雄一,栗坂 健一,(JAEA)
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Fracture Control PRA Resilience index Sodium-cooled Fast Reactor
桑原 悠士,出町 和之,笠原 直人,陳 実,(東京大),西野 裕之,小野田 雄一,栗坂 健一,(JAEA)
発刊日:
公開日:
キーワードタグ:
Fracture Control PRA Resilience index Sodium-cooled Fast Reactor
In order to quantitatively evaluate the ability of a nuclear plant to recover its safety functions, we are developing a method to simulate accident management in chronological order according to an accident scenario, rather than simply evaluating the probability, and to evaluate whether or not a major accident will eventually occur, i.e., whether or not the minimum necessary safety functions can be recovered within a time limit. In this presentation, we will discuss the development of a method to evaluate w...
英字タイトル:
Visualizing method for resilience of nuclear power plant
英字タイトル:
Visualizing method for resilience of nuclear power plant
第17回
破壊制御技術によるレジリエンス向上効果のレジリエンス指標を 用いた可視化
著者:
出町 和之,桑原 悠士,陳 実,笠原 直人,(東京大),西野 裕之,小野田 雄一,栗坂 健一,(JAEA)
発刊日:
公開日:
キーワードタグ:
Continuous Markov chain and Monte Carlo method Fracture Control Resilience Index
出町 和之,桑原 悠士,陳 実,笠原 直人,(東京大),西野 裕之,小野田 雄一,栗坂 健一,(JAEA)
発刊日:
公開日:
キーワードタグ:
Continuous Markov chain and Monte Carlo method Fracture Control Resilience Index
Our aim is to develop a technology to suppress the expansion of accident damage by improving the reactor structural resilience as a solution to the problem of restoring the safety function of structures after destruction, which has been an issue since the Fukushima Daiichi Nuclear Power Plant accident. In this research, the visualization method of resilience of nuclear structures was proposed in order to visualize the capacity to mitigate and to recover safety function loss by applying and improving the res...
英字タイトル:
Visualization of resilience improvement effect by fracture control technology using resilience index
英字タイトル:
Visualization of resilience improvement effect by fracture control technology using resilience index