176件が見つかりました。

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第17回
AIを用いた異常予兆検知システムの開発 (1)異常予兆検知AI技術「2段階オートエンコーダ」
著者:
内藤 晋,田口 安則,加藤 佑一,中田 康太,(東芝),名倉 伊作,富永 真哉,三宅 亮太,青木 俊夫,宮本 千賀司,高戸 直之,(東芝ESS)
発刊日:
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キーワードタグ:
In large-scale power plants such as nuclear and thermal power plants, thousands of sensors are installed to monitor the performance and health of the plant. However, it is difficult for operators to monitor all sensor values at all times. Therefore, Toshiba has developed a unique AI technology that comprehensively monitors thousands of sensor values and detects possible abnormalities earlier than humans. In a power plant, there are major fluctuations in sensor values during operation and minute fluctuations...
英字タイトル:
Development of anomaly detection system using AI Anomaly detection AI technology, two-stage autoencoder
第17回
AIを用いた異常予兆検知システムの開発 (2)2段階オートエンコーダの発電所データでの評価
著者:
田口 安則,内藤 晋,加藤 佑一,中田 康太,(東芝),富永 真哉,名倉 伊作,三宅 亮太,青木 俊夫,寺門 優介,高戸 直之,高森 由己夫,(東芝ESS),大熊 栄一,(東芝デジタル&コンサルティング)
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In power plants, a large number of sensors are installed and the measured values are used to control and operate the plants. Although operators monitor the measured values for daily operation and maintenance, the number that can be visually confirmed is limited. So far, we have proposed two-stage autoencoder for anomaly detection. To evaluate its effectiveness, it and simple autoencoder as a comparison method were applied to the operational data of a power plant. As a result, deterioration of a thermometer ...
英字タイトル:
Development of Anomaly Detection System using AI (2) Evaluation of two-stage autoencoder using power plant data
第17回
Anisotropic distribution of solute elements in ion - irradiated reactor pressure vessel model alloy
著者:
Ba Vu Chinh NGUYEN,Kenta MURAKAMI, Phongsakorn PRAK TOM, Liang CHEN,(長岡技科大)
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Atom probe tomography (APT) has been performed on Fe-1.4Mn0.6Ni (at%) model alloy to study solute elements behavior under 2.8 MeV Fe ions at 400 0C. Orientation imaging microscopy (OIM) analysis is applied on the detector hit map to determine the pole figure supporting for orientation calculation. The three-dimensional images show that Mn and Ni solute atoms are distributed close to some certain planes, namely <111> and <100> families. This arrangement of solute atoms on the habit planes of interstitial loo...
英字タイトル:
Anisotropic distribution of solute elements in ion - irradiated reactor pressure vessel model alloy
第17回
ATENAによる産業界の自主的安全性向上
著者:
示野 哲男,(原子力エネルギー協議会)
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原子力エネルギー協議会(ATENA)は、原子力発電所の安全性に関する共通的な技術課題に取り組 み、自主的に効果ある安全対策を立案し、事業者の現場への導入を促すことにより原子力発電所の安 全性をさらに高い水準に引き上げることを目指して活動している。ATENA の活動状況について、いくつか具体例を示しながら紹介する。...
英字タイトル:
Nuclear Industry’s Voluntary Safety Improvement with the Leadership of ATENA
第17回
BWR炉内構造物等点検評価ガイドライン 炉心シュラウド・ シュラウドサポートの改訂方針
著者:
三橋 忠浩,島津 忠昭,(東芝ESS),小林 広幸,(日本原電),菊川 浩,神長 貴幸,(東京電力),椿 正昭,内山 好司,(日立GE),佐藤 寿志,(原子力安全推進協会)
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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]....
英字タイトル:
Guideline for BWR Inspection Program Revision Policy of Guidelines for Core Shroud and Shroud Support
第17回
cosα法によるX線残留応力測定における入射角揺動の適用効果の調査
著者:
内山 宗久,(パルステック工業)
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It is known that materials with large grain size are difficult materials to measure the residual stress by X-rays. Materials in maintenance industry are sometimes large grain sized materials, electromagnetic steel sheets are as well. In this study, we show the measurement results of improve the accuracy of the measurement, residual stress by multi angles oscillation x-ray diffraction....
英字タイトル:
A study for the oscillation effect of x-ray irradiation angle inresidual stress measurement by the cosα method
第17回
Integrating deep learning-based object detection and optical character recognition for automatic extraction of link information from piping and instrumentation diagrams
著者:
董 飛艶,陳 実,出町 和之,(東京大),橋立 竜太,高屋 茂,(JAEA)
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Piping and Instrumentation Diagrams (P&IDs) contain information about the piping and process equipment together with the instrumentation and control devices, which is essential to the design and management of Nuclear Power Plants (NPPs). There are abundant complex objects on P&IDs, with imbalanced distribution of these objects and their linked information across different diagrams. The complexity of P&IDs thus is increased which make automatic identification difficult. Therefore, the content of P&IDs is gen...
第17回
IoTを活用した高度な振動診断  ~無線ネットワーク型設備診断システムの紹介~
著者:
吉永 岳,(旭化成エンジニアリング)
発刊日:
公開日:
キーワードタグ:
The evolution of IoT technology in recent years has been remarkable, and its use is accelerating in various situations in our lives. Under these circumstances, there is an urgent need to utilize IoT as an issue for production efficiency, quality improvement, and safe and stable production even at production sites. To realize stable operation of production equipment, it’s important to detect signs of equipment failure in advance and take appropriate countermeasures to minimize outage loss of equipment. Produ...
英字タイトル:
Advanced vibration diagnosis using IoT ~Introduction of mesh-type wireless vibration monitoring system~
第17回
IRIDMを活用した原子力複合災害を考慮した事業継続計画の提案
著者:
荒木 浩考,(長岡技科大),村上 健太,(東京大)
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Nowadays, companies and educational institutions are required to prepare and respond to natural disasters with Business Continuity Plans (BCP). However, many of the BCP currently being formulated focused only on the natural disasters. Therefore, this study aims to develop the framework of BCP and its formulation method considering the compound risk of nuclear and natural disasters by utilizing the IRIDM process. The IRIDM process is to optimize decision-making for continuously improving the safety of Nuclea...
英字タイトル:
Development of Business Continuity Plan Considering the Compound Risk of Nuclear Disaster Based on IRIDM process
第17回
JSME シビアアクシデント時の構造健全性評価ガイドライン (BWR鉄筋コンクリート製格納容器編)の概要
著者:
深井 新太郎,正木 洋,(東芝ESS),永田 徹也,(日立GE)
発刊日:
公開日:
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JSME シビアアクシデント時の構造健全性評価ガイドラインのうち BWR 鉄筋コンクリート製格納容器(RCCV)編について、RCCV のコンクリート部、ライナ部、鋼製耐圧部についての耐圧・耐漏えい性評価概要を記述する。 ...
英字タイトル:
Summary of Structural Integrity Evaluation Guideline under Severe Accident Condition (BWR Reinforced Concrete Containment)