![...](/img/main_bg8.jpg)
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
発刊日:
公開日:
キーワードタグ:
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
発刊日:
公開日:
キーワードタグ:
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
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
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
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. 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:
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,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
発刊日:
公開日:
キーワードタグ:
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
発刊日:
公開日:
キーワードタグ:
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
第10回
耐熱磁気センサの開発
著者:
髙屋 茂,Shigeru TAKAYA,荒川 尚,Hisashi ARAKAWA,欅田 理,Satoshi KEYAKIDA
発刊日:
公開日:
キーワードタグ:
Elevated temperature Flux gate sensor High Curie point Permendur s Degradation monitoring
髙屋 茂,Shigeru TAKAYA,荒川 尚,Hisashi ARAKAWA,欅田 理,Satoshi KEYAKIDA
発刊日:
公開日:
キーワードタグ:
Elevated temperature Flux gate sensor High Curie point Permendur s Degradation monitoring
A heat-resistant flux gate magnetic sensor has been developed. Permendur, which has high Curie point, is employed as the magnetic core material and the detection method of the external magnetic field is modified. The characteristics of the developed magnetic sensor up to 500 oC were evaluated. The sensor output increased linearly with the external magnetic field in the range of ±5 G and the standard deviation at 500 oC was about 0.85G. ...
英字タイトル:
Development of Heat-resistant Magnetic Sensor
英字タイトル:
Development of Heat-resistant Magnetic Sensor
米国機械学会(ASME)では、従来からリスク情報を活用するための規格基準類や、非軽水炉型革新炉を対象に含めた維持規格の開発整備が進められており、設計分野でも非原子力分野も対象に含め、リスク情報を活用し設計の合理化を目指す規格の新規策定のための検討が精力的に行われている。このうち、著者が開発整備に関わっているCode Case N-875及びSection XI, Division 2について概要を紹介する。...
論文
高温磁気センサの開発
著者:
髙屋 茂,Shigeru TAKAYA,荒川 尚,Hisashi ARAKAWA,欅田 理,Satoshi KEYAKIDA
発刊日:
公開日:
キーワードタグ:
Differential Permeability Flux Gate Sensor Heat Resistance Oxidation Permendur
髙屋 茂,Shigeru TAKAYA,荒川 尚,Hisashi ARAKAWA,欅田 理,Satoshi KEYAKIDA
発刊日:
公開日:
キーワードタグ:
Differential Permeability Flux Gate Sensor Heat Resistance Oxidation Permendur
A magnetic sensor which can be applied to measurement at elevated temperature was newly developed. It is a kind of flux gate magnetic sensor. Permendur was employed for a magnetic core instead of Permalloy which is commonly used because Permendur has much higher Curie point, about 1000oC. Heat resistant ceramic coating Cu wires were used for coils. External magnetic field is detected by shift of peak position of differential permeability during induction of triangular excitation current. A magnetic co...
英字タイトル:
Development of High Temperature Magnetic Sensor
英字タイトル:
Development of High Temperature Magnetic Sensor
第12回
高速炉機器の信頼性評価に関するガイドラインの整備
著者:
髙屋 茂,Shigeru TAKAYA,町田 秀夫,Hideo MACHIDA,神島 吉郎,Yoshio KAMISHIMA
発刊日:
公開日:
キーワードタグ:
Creep-Fatigue Interaction FBR ISI Passive Components Structural Reliability
髙屋 茂,Shigeru TAKAYA,町田 秀夫,Hideo MACHIDA,神島 吉郎,Yoshio KAMISHIMA
発刊日:
公開日:
キーワードタグ:
Creep-Fatigue Interaction FBR ISI Passive Components Structural Reliability
This paper describes the outline of the guidelines on structural reliability evaluation for the passive components of the fast breeder reactor (FBR). The guidelines are now being prepared by the working group for the system based code in the Japan society of mechanical engineers. They consist of five chapters, which are “General rules”, “Reliability evaluation”, “Failure scenario setting”, “Modeling”, and “Failure probability calculation”, respectively. In the chapter of “Reliability evaluation”, the g...
英字タイトル:
Development of Guidelines for Structural Reliability Evaluation for FBR
英字タイトル:
Development of Guidelines for Structural Reliability Evaluation for FBR