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Proposal of detailed procedures of determining rational in-service inspection requirements based on system based code concept

矢田 浩基; 高屋 茂; 諸星 恭一*; 横井 忍*

Proceedings of 29th International Conference on Nuclear Engineering (ICONE 29) (Internet), 9 Pages, 2022/08




田中 正暁; 堂田 哲広; 横山 賢治; 森 健郎; 岡島 智史; 橋立 竜太; 矢田 浩基; 大木 繁夫; 宮崎 真之; 高屋 茂

第26回動力・エネルギー技術シンポジウム講演論文集(インターネット), 5 Pages, 2022/07



Development of numerical analysis codes for multi-level and multi-physics approaches in an advanced reactor design study

田中 正暁; 堂田 哲広; 森 健郎; 横山 賢治; 上羽 智之; 岡島 智史; 松下 健太郎; 橋立 竜太; 矢田 浩基

Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) (Internet), 16 Pages, 2022/03



Fundamental study on scheduling of inspection process for fast reactor plants

鈴木 正昭*; 伊藤 真理*; 橋立 竜太; 高橋 慧多; 矢田 浩基; 高屋 茂

2020 9th International Congress on Advanced Applied Informatics (IIAI-AAI 2020), p.797 - 801, 2021/07

To realize the reasonable and effective maintenance of nuclear power plants, it is essential to optimize the maintenance scheduling management from the viewpoints of both safety and efficiency. As a fundamental study, we propose an inspection-process-scheduling model that minimizes the total number of inspections in a fast reactor. In this study, we formulate the inspection-process-scheduling problem as an integer programming problem. Computing the inspection-process schedules for a simplified fast reactor plant model, we verified that the proposed model can provide the optimal schedule automatically.


「もんじゅ」点検期間長期化の要因分析及び次世代高速炉の保全合理化案の提案,2; 低温停止期間における「もんじゅ」の保全計画分析

豊田 晃大; 橋立 竜太; 高橋 慧多; 矢田 浩基; 高屋 茂

保全学, 20(2), p.95 - 103, 2021/07

It is necessary to implement reasonable maintenance based on characteristics of a nuclear power plant to achieve both high safety and high economic efficiency of the power plant. The prototype fast breeder reactor "Monju" spent most of the year on maintenance. It is important to identify causes of the prolonged maintenance of "Monju" and consider countermeasures for subsequent fast reactors. In this study, we investigate causes of the prolonged maintenance by analyzing the Monju's maintenance plan. Further, we make proposals for optimizing the maintenance of next-generation fast reactors to address the identified issues.


Development of leak before break assessment guidelines for sodium cooled fast reactors in Japan

矢田 浩基; 若井 隆純; 宮川 高行*; 町田 秀夫*

Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet), 10 Pages, 2021/07

The leak before break (LBB) assessment guidelines for sodium cooled fast reactors (SFRs) is being developed in the Japan Society of Mechanical Engineers (JSME). The major purpose of the guidelines is to provide LBB assessment procedures for pipes and vessels of SFRs that retain sodium coolant. Design features of SFRs, such as high operation temperatures and low pressure coolant-systems, are taken into account. The LBB guidelines is used in connection to the fitness-for-service code that is also being developed for SFRs in JSME. If the establishment of LBB concept is successfully demonstrated, continuous leakage monitoring will be adopted as an in-service inspection for SFR components constituting sodium coolant boundary, such as sodium retaining pipe and vessels. In this article, LBB assessment procedure and individual assessment method is introduced, and major sodium piping of Japanese SFR plant was assessed.


「もんじゅ」点検期間長期化の要因分析及び次世代高速炉の保全合理化案の提案,1; 低温停止中の「もんじゅ」のプラント工程の分析

橋立 竜太; 豊田 晃大; 高橋 慧多; 矢田 浩基; 高屋 茂

保全学, 19(4), p.115 - 122, 2021/01



Proposal of inspection rationalization method and application for sodium cooled fast reactor

矢田 浩基; 高屋 茂; 江沼 康弘

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 7 Pages, 2020/08

In order to rationalize maintenance for nuclear power plants, it is necessary to develop optimize maintenance plan by considering characteristics of each plant. In sodium-cooled fast reactor, there are constraints on inspections due to the specialty of handling sodium equipment, that is one of the important points when considering rationalization of maintenance. To solve this problem, we proposed a basic concept of maintenance optimization scheme that is a design support tool in order to develop maintenance strategy, based on "system based code". One of the proposed scheme goals is to make a concrete way of necessary assessment method. Another is to provide several combinations of design and maintenance, and information for owner in order to choose the acceptable combination. In the beginning, we are working to develop the scheme that can be applied to sodium fast reactor as the main concept of next generation reactor. In this context, primary heat transfer system (PHTS) piping of fast reactor was evaluated by the scheme. This piping was chosen because it is major significant component and the inspection have constraint conditions that need preparation work. As a result, design candidate (e.g. single and double wall piping) and inspection candidate (e.g. ultrasonic testing and continues leakage monitoring) combinations along with benefit of each cases were provided.


Development of LORL evaluation method and its application to a loop-type sodium-cooled fast reactor

今泉 悠也; 山田 文昭; 有川 晃弘*; 矢田 浩基; 深野 義隆

Mechanical Engineering Journal (Internet), 5(4), p.18-00083_1 - 18-00083_11, 2018/08



Effect of 3-D initial imperfections on the deformation behaviors of head plates subjected to convex side pressure

矢田 浩基; 安藤 勝訓; 月森 和之; 一宮 正和*; 安濃田 良成*

Proceedings of 2018 ASME Pressure Vessels and Piping Conference (PVP 2018), 9 Pages, 2018/07



Leak rate tests of penetrate cracked head plates and modeling of head plate thickness distribution for 3-D analyses

月森 和之*; 矢田 浩基; 安藤 勝訓; 一宮 正和*; 安濃田 良成*

Proceedings of 12th International Conference on Asian Structure Integrity of Nuclear Components (ASINCO-12) (CD-ROM), p.105 - 121, 2018/04




矢田 浩基; 高屋 茂; 若井 隆純; 仲井 悟; 町田 秀夫*

日本機械学会論文集(インターネット), 84(859), p.17-00389_1 - 17-00389_15, 2018/03



Experimental study on the deformation and failure of the bellows structure beyond the designed internal pressure

安藤 勝訓; 矢田 浩基; 月森 和之; 一宮 正和*; 安濃田 良成*

Journal of Pressure Vessel Technology, 139(6), p.061201_1 - 061201_12, 2017/08

 被引用回数:1 パーセンタイル:8.14(Engineering, Mechanical)



Experimental study on behaviours of two-ply bellows subjected to pressure and displacement loads

月森 和之; 安藤 勝訓; 矢田 浩基; 一宮 正和*; 安濃田 良成*; 荒川 学*

Transactions of 24th International Conference on Structural Mechanics in Reactor Technology (SMiRT-24) (USB Flash Drive), 10 Pages, 2017/08



Experimental demonstration of failure modes on bellows structures subject to internal pressure

安藤 勝訓; 矢田 浩基; 月森 和之; 一宮 正和*; 安濃田 良成*

Proceedings of 2017 ASME Pressure Vessels and Piping Conference (PVP 2017) (CD-ROM), 11 Pages, 2017/07



Failure mode of ED and AD type head plates subject to convex side pressure

矢田 浩基; 安藤 勝訓; 月森 和之; 一宮 正和*; 安濃田 良成*

Proceedings of 2017 ASME Pressure Vessels and Piping Conference (PVP 2017) (CD-ROM), 8 Pages, 2017/07



会議報告; 2016 ASME Pressure Vessels & Piping Conference (PVP2016)

矢田 浩基

保全学, 15(3), P. 86, 2016/10

2016年7月17日$$sim$$21日の5日間、カナダのバンクーバーにて開催された"2016 ASME Pressure Vessels & Piping Conference"の概要を報告する。


Experimental study on ultimate strength of single and double type bellows under internal pressure

安藤 勝訓; 矢田 浩基; 月森 和之; 一宮 正和*; 安濃田 良成*

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 8 Pages, 2016/07



Experimental study on ultimate strength of a ellipsoidal dished head plate under pressure on convex surface

矢田 浩基; 安藤 勝訓; 月森 和之; 一宮 正和*; 安濃田 良成*

Proceedings of 2016 ASME Pressure Vessels and Piping Conference (PVP 2016) (Internet), 7 Pages, 2016/07



Study on behaviours of multi-ply bellows subjected to pressure and displacement loads

月森 和之; 安藤 勝訓; 矢田 浩基

Transactions of 23rd International Conference on Structural Mechanics in Reactor Technology (SMiRT-23) (USB Flash Drive), 10 Pages, 2015/08


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