近澤 佳隆
著者に関連した記事は7件です。
更新情報
第14回
PIRT手法を用いた研究開発段階発電用原子炉の保守管理における要検証劣化メカニズムの抽出方法に関する検討
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田中 正暁,Masaaki TANAKA
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Degradation Mechanism Graded Approach Operational Experience Sodium-Cooled Fast Reactor
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田中 正暁,Masaaki TANAKA
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Degradation Mechanism Graded Approach Operational Experience Sodium-Cooled Fast Reactor
In a previous paper, the authors discussed maintenance management suitable to R&D-level nuclear power plants, and made proposals. One of key proposals was to enhance knowledge on potential degradation mechanisms specific to a new reactor type by accumulating operational experience. It was noted that validation of R&D knowledge in actual plant conditions is important. In this study, a method for identifying degradation mechanisms to be validated by the PIRT (Phenomena Identification and Ranking Table) p...
英字タイトル:
Study on a Method for Identifying Degradation Mechanisms to be Validated in Maintenance Management of R&D-Level Nuclear Power Plants Using the PIRT Process
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Study on a Method for Identifying Degradation Mechanisms to be Validated in Maintenance Management of R&D-Level Nuclear Power Plants Using the PIRT Process
第14回
レジリエンス評価法の高速炉への適用性に関する基礎的検討
著者:
鈴木 正昭,Masaaki SUZUKI,出町 和之,Kazuyuki DEMACHI,高屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA
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Fast Reactor Resilience Response Margin Response Reliability
鈴木 正昭,Masaaki SUZUKI,出町 和之,Kazuyuki DEMACHI,高屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA
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Fast Reactor Resilience Response Margin Response Reliability
We have proposed new indices for evaluating resilience, that is, the response margin and response reliability of a nuclear power plant during an accident and detailed procedure for assessing those indices. In this study, the resilience of a simple fast reactor plant model is evaluated according to the indices. The applicability of the resilience evaluation method to fast reactor plants is then discussed from the viewpoints of reflecting the characteristics of each reactor type....
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Fundamental Study on Applicability of Resilience Evaluation Method to Fast Reactor Plants
英字タイトル:
Fundamental Study on Applicability of Resilience Evaluation Method to Fast Reactor Plants
論文
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
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Maintenance Classification Maintenance Program Sodium-Cooled Fast Reactor
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
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Maintenance Classification Maintenance Program Sodium-Cooled Fast Reactor
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. Finally, an example that the proposal was applied to setting maintenance program of sodium-cooled fast reactor was presented. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (1)基本要件
著者:
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
Maintenance Classification Maintenance Program Sodium-Cooled Fast Reactor
髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
Maintenance Classification Maintenance Program Sodium-Cooled Fast Reactor
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage was first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (1) Basic Requirements
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (1) Basic Requirements
第13回
研究開発段階発電用原子炉の特徴を考慮した 保守管理の提案 (2)適用事例
著者:
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
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キーワードタグ:
maintenance management preventive maintenance reactor at R&D stage
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,林田 貴一,Kiichi HAYASHIDA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO,山下 厚,Atsushi YAMASHITA
発刊日:
公開日:
キーワードタグ:
maintenance management preventive maintenance reactor at R&D stage
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, requirements on maintenance program of NPP at R&D stage were clarified and an example that the proposal was applie...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (2) case study
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (2) case study
第14回
研究開発段階発電用原子炉の特徴を考慮した保守管理の提案 (3) 配管支持構造物への適用事例
著者:
相澤 康介,Kosuke AIZAWA,髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
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maintenance management piping support reactor at R&D stage sodium cooled reactor
相澤 康介,Kosuke AIZAWA,髙屋 茂,Shigeru TAKAYA,近澤 佳隆,Yoshitaka CHIKAZAWA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
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maintenance management piping support reactor at R&D stage sodium cooled reactor
One of important mission of nuclear power plants (NPP) at R&D stage is to develop maintenance program for commercial reactors step by step securing safety. Basic principles of maintenance management for NPP at R&D stage were proposed. In this paper, applications for maintenance program on piping support of prototype sodium cooled fast breeder reactor Monju are studied on the basis of the proposed basic principles of maintenance management for NPP at R&D stage. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (3) Application to piping support
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (3) Application to piping support
第14回
研究開発段階発電用原子炉の特徴を考慮した保守管理の提案 (4)ナトリウム弁の事例
著者:
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
発刊日:
公開日:
キーワードタグ:
maintenance management preventive maintenance reactor at R&D stage
近澤 佳隆,Yoshitaka CHIKAZAWA,髙屋 茂,Shigeru TAKAYA,田川 明広,Akihiro TAGAWA,久保 重信,Shigenobu KUBO
発刊日:
公開日:
キーワードタグ:
maintenance management preventive maintenance reactor at R&D stage
A maintenance management suitable to nuclear power plants (NPP) at R&D stage was discussed. Objectives of maintenance management of NPP at R&D stage were first clarified. Next, applicability of codes for maintenance management of commercial NPP to NPP at R&D stage was discussed. Then, requirements and consideration for maintenance management of NPP at R&D stage was proposed. In this paper, maintenance program for sodium valves are investigated. ...
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (4) case study on sodium valves
英字タイトル:
Proposal of Maintenance Management of Nuclear Power Plants at R&D Stage by Taking Account of Their Features (4) case study on sodium valves