The current edition of “Guideline of Inspection and Evaluation for Reactor Internals issued by Japan Nuclear Safety Institute (JANSI) consists of inspection target, inspection method, and evaluation. Recently, the guideline is revised based on the safety function of the Reactor Internals, domestic operation experience, and the new knowledge. In this report, summary of “Guidelines of Inspection and Evaluation for Reactor Internals [Core Shroud] and [Shroud Support]....
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Guideline for BWR Inspection Program Revision Policy of Guidelines for Core Shroud and Shroud Support

Nuclear power plants have been restarted, and trials on driving injunctions are being made in some places in Japan. As in the case of responding to Pyroclastic flow, the recent issue has shifted from the academic task to the inter-discipline problem between science and society, such as matching risk recognition with society. In the paper, we would like to explain the discussion points and find out the direction of solution by looking at some experiences and achievements in the areas other than nuclear secto...
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Nuclear Power Trials, Issue and Arguments -To reduce risk of lawsuit-

Nuclear power plants have been restarted, and trials on driving injunctions are being made in some places in Japan. As in the case of responding to Pyroclastic flow, the recent issue has shifted from the academic task to the inter-discipline problem between science and society, such as matching risk recognition with society. In the paper, we would like to explain the discussion points and find out the direction of solution by consolidating the opinions of law experts and experts in nuclear technology....
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Nuclear Power Trials, Issue and Arguments -Why was a nuclear power plant stopped-

原発の運転差し止め裁判の課題を調査してきた。裁判では、原子力規制委員会が認めた審査の合格に 反論し、運転の差し止めを請求する訴訟が多発し、判決は様々な判断を示している。本検討会では、何が技術的課題なのかを明確にして、裁判で説明しきていない技術的論点について、正論を示すことを 狙って活動している。本報告では原発の再稼働が裁判で争われる構図を概観し、そこに含まれる問題 点について報告したい。 We have investigated the issue of the nuclear power plant injunction trial. The court may have argued against the “passed examination” conclusion accepted by the NRA. Many lawsuits have been filed to stop the operation of nuclear power plants. Judgments in court show various decisions. In this study group, we a...
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Nuclear Power Trials, Issue and Arguments No.1 Technical Issue - External Events-

原発の運転差し止め裁判の課題を調査してきた。裁判では、原子力規制委員会が認めた審査の合格に反論し、運転の差し止めを請求する訴訟が多発し、判決は様々な判断を示している。本検討会では、何 が技術的課題なのかを明確にして、裁判で説明しきていない技術的論点について、正論を示すことを 狙って活動している。本報告では、特に外的事象、自然災害を対象に、どのような判断が示され、そこにどのような論点があるのか明確にした。 We have investigated the issue of the nuclear power plant injunction trial. The court may have argued against the “passed examination” conclusion accepted by the NRA. Many lawsuits have been filed to stop the operation of nuclear power plants. Judgments in court show various decisions. In this study group,...
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Nuclear Power Trials, Issue and Arguments No.2 Technical Issue - External Events-

Thermal embrittlement of cast austenitic stainless steel components from the decommissioned advanced thermal prototype reactor Fugen has been characterized. Cast stainless steel materials were obtained from recirculation pump casing. The actual time at temperature for the materials was 138,000 h at 275 oC. The “Fugen” material show modest decrease in Charpy-impact properties and a small increase in micro-Vickers hardness in ferrite phase because of thermal aging at relatively low service temperatures. ...
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Research of Estimation Method of Thermal Aging Embrittlement on Cast Austenitic Stainless Steel

Abstract The fusion reactor is expected as a next-generation electric source to resolve electricity shortage. The reduce d activation steel F82H has been considering as the structural material for blanket modules set in fusion reactors. In t he case of welding for the steel, its demanded to minimize the heat affected zone (HAZ). Therefore, laser beam welding ( LBW) has been considering as one of welding methods to construct the modules. The objectives of this investigation are t o clarify the critical cond...
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Study on Applicability of Laser Beam Welding for Reduced Activation Ferritic Steel F82H

To strengthen the operation and maintenance technology of Rokkasho fuel cycle facilities,J-tech developed J- tech Hybrid Compact Simulator (J-HySIM) in October 2018. Not only a normal operation mode but also abnormal operation ,maintenance mode and a part of severe accident mode of this facilities were experienced by 200 operators and 60 maintenance engineers.Furthermore two instructers are being brought up.With three years training with this machine, operation and maintenance skill were improved efficientl...
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Program and achievement for the training of operation and maintenance with “J-tech Hybrid Compact Simulator (J-HySIM)”

It is necessary to confirm whether the feed water nozzle inside corner has crack by eddy current testing, to enable long-term operation of a plant. Therefore, we performed eddy current testing using various types of specimen to collect basic data (probability and length measurement accuracy) of the eddy current testing methods, complying with JEAG4217. As a result, eddy current testing was effective for the inspection of feed water nozzle inside corner. ...
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Eddy current testing technique for feed water nozzle inside corner of nuclear reactor pressure vessel

According to the design standards of nuclear equipment, ductile fracture is assumed as the failure mode due to monotonic loading in the elastic-plastic region, but it is known that failure mode called local failure occurs at the part with high stress triaxiality. In the past, the authors have proposed a fracture surface that can uniformly evaluate transition of failure modes from ductile fracture to local failure. This research proposes the extension method of the fracture surface to creep region. ...
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Investigation on extension of local failure evaluation method in plastic region to creep region