江沼 康弘
著者に関連した記事は5件です。
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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）
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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）
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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
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論文
次世代炉の合理的な設計のための 保全の観点からのプラント設計上の課題抽出手法の提案
著者:
橋立 竜太 Ryuta HASHIDATE 矢田 浩基 Hiroki YADA 高屋 茂 Shigeru TAKAYA 江沼 康弘 Yasuhiro ENUMA
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Design Issues Maintenance Period Maintenance Precondition Monju Next-Generation Reactors
橋立 竜太 Ryuta HASHIDATE 矢田 浩基 Hiroki YADA 高屋 茂 Shigeru TAKAYA 江沼 康弘 Yasuhiro ENUMA
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Design Issues Maintenance Period Maintenance Precondition Monju Next-Generation Reactors
In this paper, we propose a new method for extracting design issues on maintenance. Maintenance periods might be prolonged due to design issues. In the proposed method, maintenance preconditions are extracted by organizing the design information. A maintenance schedule is created by using extracted maintenance preconditions. If the created maintenance schedule doesn't achieve target periods, design issues could be extracted from the viewpoint of maintenance precondition. A simple example using "Monju" desig...
英字タイトル:
Proposal of a Method of Extracting Design Issues on Maintenance for the Rational Design of Next-Generation Reactors
英字タイトル:
Proposal of a Method of Extracting Design Issues on Maintenance for the Rational Design of Next-Generation Reactors
第16回
竜巻飛来物による機器破損確率の評価 -簡易評価法による実プラントを対象とした試算-
著者:
相澤 康介,江沼 康弘,（JAEA）,山田 和彦,（鹿島建設,（山口大））
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Failure probability Missile location Tornado missile Tornado missile management Vortex model
相澤 康介,江沼 康弘,（JAEA）,山田 和彦,（鹿島建設,（山口大））
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Failure probability Missile location Tornado missile Tornado missile management Vortex model
An evaluation of failure probability for facilities in a real plant subjected to tornado missiles was introduced based on simple calculation. Impact speeds of the tornado missiles to the plant facility were calculated, assuming several initial locations for them and Rankine's model or Fujita's model as a tornado vortex model. Failure probability of each facility subjected to the tornado missiles was quantitatively evaluated, taking account of probabilities of tornado strike to the plant, number of missiles ...
英字タイトル:
Failure probability of plant facilities subjected to tornado missiles - An evaluation for a real plant based on simple calculation -
英字タイトル:
Failure probability of plant facilities subjected to tornado missiles - An evaluation for a real plant based on simple calculation -
第17回
革新炉の統合的な設計評価と最適化に資する ナレッジマネジメントシステムの開発
著者:
近藤 佑樹,橋立 竜太,浜瀬 枝里菜,江連 俊樹,光元 里香,矢田 浩基,江沼 康弘,（JAEA）
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ARKADIA Fast Reactor Knowledge Base Knowledge Management System Maintenance Optimization Scheme
近藤 佑樹,橋立 竜太,浜瀬 枝里菜,江連 俊樹,光元 里香,矢田 浩基,江沼 康弘,（JAEA）
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ARKADIA Fast Reactor Knowledge Base Knowledge Management System Maintenance Optimization Scheme
JAEA has started the development of Advanced Reactor Knowledge-and AI-aided Design Integration Approach through the whole plant lifecycle (ARKADIA) that performs integrated design evaluation and optimization from various viewpoints such as safety, economy, and maintainability using risk information, in order to dramatically improve the development efficiency of innovative reactors. In this paper, we report the concept of a knowledge management system to support integrated design evaluation and optimization,...
英字タイトル:
Development of knowledge management system contributing to integrated design evaluation and optimization of innovative reactors
英字タイトル:
Development of knowledge management system contributing to integrated design evaluation and optimization of innovative reactors
第12回
高速炉プラント（「もんじゅ」）の安全性確保の考え方
著者:
岡田 俊親,Toshichika OKADA,市川 健太,Ichikawa KENTA,二神 敏,Futagami SATOSHI,江沼 康弘,Yasuhiro ENUMA,宮川 明,Akira MIYAKAWA,堺 公明,Takaaki SAKAI,中井 良大,Ryodai NAKAI
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Accident Management Fast Breeder Reactor Monju Safety Requirements Severe Accident
岡田 俊親,Toshichika OKADA,市川 健太,Ichikawa KENTA,二神 敏,Futagami SATOSHI,江沼 康弘,Yasuhiro ENUMA,宮川 明,Akira MIYAKAWA,堺 公明,Takaaki SAKAI,中井 良大,Ryodai NAKAI
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Accident Management Fast Breeder Reactor Monju Safety Requirements Severe Accident
Japan Atomic Energy Agency (JAEA) has organized “Pier Review Committee of Monju” consisting of experts on sodium cooled reactors and nuclear safety assessment in order to discuss and propose safety requirements for the prototype FBR Monju. JAEA is now researching the optimum plan in accordance with these safety requirements. Adopting another independent interlocking-system for the back-up shut-down system can reduce the accident risk of ULOHS: unprotected loss of heat sink. The heat transfer system of ...
英字タイトル:
Safety Requirements the Prototype Fast Breeder Reactor “Monju”
英字タイトル:
Safety Requirements the Prototype Fast Breeder Reactor “Monju”