It is necessary to improve not only plant system but also human system for maintenance to optimize maintenance for industrial plants like nuclear power plants. Codes and standards for design and construction of plant system have been already well developed. On the contrary, standardization of documents relating to human system including maintenance implementation plan, field work procedures etc. have poorly developed. So we have established the special committee in Japan Society of Maintenology to standardi...
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Necessity and Direction of Consideration of Maintenance Standardization

六ヶ所再処理工場セル内における遠隔乾式切断技術の開発 Development of remote dry cutting technology in cells of Rokkasho reprocessing plant 二菱重工業株式会社 大中 雅侑 Masayuki ONAKA Member 二菱重工業株式会社 井上 哲徳 Akinori INOUE Non-Member 日本原燃株式会社 飯田 雅之 Masayuki IIDA Non-Member 日本原燃株式会社 成田 祐一 YuichiNAR......
英字タイトル:
Development of remote dry cutting technology in cells of Rokkasho reprocessing plant

An analysis system capable of monitoring chemical components in real time was constructed by combining an on-line monitoring technique of chemical components based on spectroscopic analysis and a new spectral analysis technique. By using this technology, it is possible to shorten the analysis time and reduce the amount of waste liquid without requiring sampling or remote analysis operations....

The building of the nuclear power plant has a through hole for passing piping. A sealant is filled in the gap between the through hole and the pipe to secure the sealing property of the portion. When an earthquake occurs, relative displacement occurs in the through hole and the pipe. There is a concern that the seal material may be damaged if the relative displacement is large. Therefore, we have developed a seal structure with good displacement followability....
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Development of seismic improvement seal structure for nuclear plant building

In accordance with of the Reactor Regulation Act, the Operational Safety Program is requird to be established in order to keep the Nuclear Power Plant (NPP) in safe operation. The Licensee shall maintain the component, system and plant in the Limiting Condition of Operation (LCO), which is one of the provision of the Operational Safety Program, by monitoring the plant parameter and component condition in the Main Control Room or at local through the plant operation period including startup and shutdown. In ...
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Improvement of technical specification management at Nuclear Power plant

To confirm the soundness of component of nuclear power plants, NDE techniques are applied. Especially, ECT is applied as the volumetric inspection for heat transfer tubes of heat exchangers, and as the surface inspection for weld zone. The materials of them have good corrosion resistance, but they had many experience of occurring flaw because plant-operating period became so longer. We developed various types of high performance ECT probe in order to detect every types of flaws which are occurred, and which...
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History of development of high performance ECT probe applied in nuclear power plants

Human factors engineering process is applied in design phase from planning to commission and operation. Twelve elements of human factors engineering need to be linked closely between each information necessary for each element implementation. When a design information is changed, each element needs to be reevaluated in the design process. A design support system for the human factors engineering process, developed and utilized internally by Mitsubishi heavy industries, LTD, is introduced in this paper. This...
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Development of human factors engineering design support system for nuclear power plants

加圧水型原子炉(PWR)の応力腐食割れに対して国内外で様々な工法が開発され、実機に適用されている。原子炉容器出入口管台の600合金使用部位の応力腐食割れ対策として、原子炉容器出入口管台 INLAY 工法が開発され、実機への適用実績がある。2018年3月～4月に九州電力掬川内原子力発電所1号機に対し、本工法が適用された。...

As "A historic heritage related to maintenance technology and a cultural heritage of humankind with the aim of encouraging the development, dissemination and contribution to society of Maintenology." the automatic ultrasonic flaw detection machine for reactor vessel (A-UT Machine) was recognized as the first heritage. The A-UT machine was used for the first time in the world for the inspection of reactor vessels of PWR nuclear power plants in 1995. Since then, improvements have been made to improve the accu...
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Automatic ultrasonic flaw detection machine for reactor vessel History of A-UT Machine Development

Bare metal visual examination (BMV) is required for dissimilar metal welds of class 1 component for PWR (Pressurized Water Reactor) in inspection and evaluation guidelines published by Japan Nuclear Safety Institute (JANSI). However, there have been no guidelines which specify the procedures for BMV. In 2021, the guideline stipulating specific procedures for BMV were established by JANSI. This guideline includes both lessons-learned related to the boric acid corrosion on reactor pressure vessel upper head a...
英字タイトル:
Establishment of Bare Metal Visual Examination Guideline for Class 1 Pressure Vessels such as Reactor Pressure Vessel