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Attention-based time series analysis for data-driven anomaly detection in nuclear power plants

Dong, F.*; Chen, S.*; 出町 和之*; 吉川 雅紀; 関 暁之; 高屋 茂

Nuclear Engineering and Design, 404, p.112161_1 - 112161_15, 2023/04


To ensure nuclear safety, timely and accurate anomaly detection is of utmost importance in the daily condition monitoring of Nuclear Power Plants (NPPs), as any slight anomaly in a plant may result in an irreversible and serious accident, as well as high costs of maintenance and management. Nevertheless, due to the unique inherent attributes of anomalies, the difficulty of automatic detection in NPPs is increased. Previous model-driven anomaly detection approaches required skilled priori knowledge, leading to their limited usability. Commonly adopted deep learning-based data-driven anomaly detection approaches may not easily acquire the most relevant features when dealing with sensor data containing redundant information with uneven distribution of anomalies. To alleviate these issues, this paper propose an attention-based time series model for anomaly detection to ensure safety in NPPs. First, we employ one-dimension convolutional neural network (1D-CNN) backbone for feature extraction to preserve original inherent features of time series inputs. Subsequently, we originally adopt soft-attention mechanism to automatically extract the most relevant temporal features considering the specificity of anomaly detection in NPPs. The performance of the proposed model was experimentally validated on the High Temperature Gas-cooled Reactor (HTGR) anomaly case dataset simulated using the analytical code. The experimental results indicate that the proposed model was capable of detecting anomalies in NPPs with superior performance to the baseline model, while ensuring fast detection at short time steps.


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



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.


「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.


A Simplified method for evaluating sloshing impact pressure on a flat roof based on Wagner's theory

高屋 茂; 藤崎 竜也*

Mechanical Engineering Journal (Internet), 7(3), p.19-00526_1 - 19-00526_10, 2020/06



Influence of dead weight and internal pressure to seismic buckling probability of fast reactor vessels

高屋 茂; 佐々木 直人*

Mechanical Engineering Journal (Internet), 7(3), p.19-00549_1 - 19-00549_9, 2020/06



Development of prototype reactor maintenance, 3; Application to valves of sodium-cooled reactor prototype

近澤 佳隆; 高屋 茂; 田川 明広; 久保 重信

Proceedings of 2019 International Congress on Advances in Nuclear Power Plants (ICAPP 2019) (Internet), 6 Pages, 2019/05



Proposal of a simple evaluation method for sloshing impact pressure on flat roofs

高屋 茂; 藤崎 竜也*

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07




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



Creep-fatigue evaluation method for weld joints of Mod.9Cr-1Mo steel, 1; Proposal of the evaluation method based on finite element analysis and uniaxial testing

安藤 勝訓; 高屋 茂

Nuclear Engineering and Design, 323, p.463 - 473, 2017/11


 被引用回数:2 パーセンタイル:22.85(Nuclear Science & Technology)



Numerical analysis of flow-induced vibration of large diameter pipe with short elbow

高屋 茂; 藤崎 竜也*; 田中 正暁

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



Load and resistance factor design approach for seismic buckling of fast reactor vessels

高屋 茂; 佐々木 直人*; 浅山 泰; 神島 吉郎*

Mechanical Engineering Journal (Internet), 4(3), p.16-00558_1 - 16-00558_12, 2017/06



Development of prototype reactor maintenance, 1; Application to piping system of sodium-cooled reactor prototype

小竹 庄司*; 近澤 佳隆; 高屋 茂; 大高 雅彦; 久保 重信; 荒井 眞伸; 桾木 孝介; 伊藤 隆哉*; 山口 彰*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04



Development of prototype reactor maintenance, 2; Application to piping support of sodium-cooled reactor prototype

荒井 眞伸; 桾木 孝介; 相澤 康介; 近澤 佳隆; 高屋 茂; 久保 重信; 小竹 庄司*; 伊藤 隆哉*; 山口 彰*

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04




高屋 茂; 近澤 佳隆; 林田 貴一; 田川 明広; 久保 重信; 山下 厚

保全学, 15(4), p.71 - 78, 2017/01




岡島 智史; 高屋 茂; 浅山 泰

日本機械学会論文集(インターネット), 83(845), p.16-00434_1 - 16-00434_13, 2017/01



Creep-fatigue evaluation method for weld joint of Mod.9Cr-1Mo steel, 2; Plate bending test and proposal of a simplified evaluation method

安藤 勝訓; 高屋 茂

Nuclear Engineering and Design, 310, p.217 - 230, 2016/12


 被引用回数:1 パーセンタイル:12.01(Nuclear Science & Technology)


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