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

In this study, stress measurements were performed using a double exposure method with hard synchrotron monochromatic X-rays, and its validity was proved. The diffractions of the shrink-?tted ring of austenitic stainless steel SUS304 were measured by the CdTe pixel detector. The used X-rays were 70, 80 and 90 keV. The measured stress distributions with the 311 diffraction of γ-Fe corresponded to the predicted result. In addition, The stress distribution of the shrink-?tted ring was measured by the CCD camera...
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Stress Measurements of Austenitic Stainless Steel using Hard Synchrotron X-Rays

In Japan Atomic Energy Agency (JAEA), an advanced fuel reprocessing for fast reactor fuel cycle are carried out in hot cells in the Chemical Processing Facility (CPF). Since hot cell is high radiation and nitric acid atmosphere, the mercury lamps with excellent radiation resistance have been used. The manufacture and import of mercury lamps will be banned in 2021; therefore, we started the development of alternative lighting. LED lamps are superior in lighting speed and power consumption compared to mercury...
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Development of radiation-resistant straight tube LED lighting at Chemical Processing Facility

The protective nets against the tornado missile are important for power plant equipment. Japan Atomic Energy Agency has developed the protective net using aramid fiber rope to aim high strength lightweight net. The net element tests and analyses were conducted to clarify the characteristic of the protective net using aramid fiber rope. The actual size net was designed based on the results of net element tests and analyses. The dynamic analysis which simulates a car crash on the designed actual size net was ...
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Development of protective net using high strength lightweight aramid for tornado missile

Prototype fast breeder reactor "Monju" accumulated maintenance, the repair experience more than 25 years after a test operation and got the knowledge that became extremely useful for the design of the fast reactor and operation and maintenance in the future. A maintenance program was introduced as a fast reactor power plant at the Stage of Research and Development, and problems such as the maintenance management became clear and examined the way of the maintenance management based on these experiences....
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Maintenance history and result of the prototype fast breeder reactor "Monju"

In order to achieve both safety and economic efficiency of a nuclear power plant, it is necessary to realize rational maintenance based on characteristics of the plant. The fast breeder prototype reactor, Monju, spent most of the year for the maintenance. It is important to identify causes of the prolonged maintenance of Monju and to investigate countermeasures for implementation of rational maintenance of a next fast reactor. In this study, causes of the prolonged maintenance of Monju during reactor cold s...
英字タイトル:
Analysis of issues related to maintenance period of the fast breeder prototype reactor Monju (1) Analysis of plant operation for maintenance of cold shutdown Monju

In order to achieve both safety and economic efficiency of a nuclear power plant, it is necessary to realize rational maintenance based on characteristics of the plant. The fast breeder prototype reactor, Monju, spent most of the year for the maintenance. It is important to identify causes of the prolonged maintenance of Monju and to investigate countermeasures for implementation of rational maintenance of a next fast reactor. In this study, causes of the prolonged maintenance of Monju during reactor cold s...
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Analysis of issues related to maintenance period in the fast breeder prototype reactor Monju (2) Analysis of plant maintenance plan

To achieve the reasonable and effective maintenance of nuclear power plants, it is essential to optimize the aging management from the viewpoints of both safety and efficiency. We propose an inspection-process-scheduling model that minimizes the number of inspection activities in a fast reactor. In this study, we formulate the inspection-process-scheduling problem as mixed integer programming and 0- integer programming problem....
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Fundamental Study on Optimal Scheduling of Inspection Process for Fast Reactor

Maintenance scheduling is currently manually handled, which is a time-consuming process because of the large number of components and constraints that must be taken into account when creating a schedule. Besides, to develop next-generation power plants with excellent operability, it is necessary to make it possible to evaluate operability and maintainability in advance at the design stage. Our objective is to develop and implement an automatic scheduling system using the mathematical technique of Operations...
英字タイトル:
Development of Inspection Process Scheduling System for Analyzing Operability of Fast Reactor