芝 小林
著者に関連した記事は4件です。
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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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BWR Core Shroud Inspection and Evaluation JANSI Guideline Reactor Internals Shroud Support
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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BWR Core Shroud Inspection and Evaluation JANSI Guideline Reactor Internals Shroud Support
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
英字タイトル:
Guideline for BWR Inspection Program Revision Policy of Guidelines for Core Shroud and Shroud Support
第15回
中性子束計測ハウジング向け渦電流探傷検証試験
著者:
小林 徳康,森川 史和,藤田 友基,松川 大介,糟谷 高志,土橋 健太郎,（東芝ESS）
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Eddy current testing Heat affected zone In-core monitor housing Non-destructive inspection Nuclear reactor
小林 徳康,森川 史和,藤田 友基,松川 大介,糟谷 高志,土橋 健太郎,（東芝ESS）
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Eddy current testing Heat affected zone In-core monitor housing Non-destructive inspection Nuclear reactor
We verified that the eddy current testing (ECT) has the enough detectability for defects on the heat affected zone (HAZ) in welding of in-core monitor (ICM) housing inner surfaces for a special inspection involved in long-term operation. It is presumed that a detectability of ECT is decreased because a HAZ of ICM housing inner surfaces is deformed by welding. We conducted full-scale defect detection tests using the simulated ICM housing specimen with the welded part, the rotational ECT probe and the probe m...
英字タイトル:
Verification of Eddy Current Testing for In-Core Monitor Housing
英字タイトル:
Verification of Eddy Current Testing for In-Core Monitor Housing
第10回
原子炉底部管台向け渦電流探傷システムの開発
著者:
芝 小林,小林 徳康,Noriyasu KOBAYASHI,芝 上野,上野 聡一,Souichi UENO,芝 千田,千田 格,Itaru CHIDA,芝 落合,落合 誠,Makoto OCHIAI,芝 藤田,藤田 友基,Tomoki FUJITA,芝 市川,市川 博也,Hiroya ICHIKAWA
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Bottom-mounted instrumentation BWR Eddy current testing PWR Stress corrosion cracking
芝 小林,小林 徳康,Noriyasu KOBAYASHI,芝 上野,上野 聡一,Souichi UENO,芝 千田,千田 格,Itaru CHIDA,芝 落合,落合 誠,Makoto OCHIAI,芝 藤田,藤田 友基,Tomoki FUJITA,芝 市川,市川 博也,Hiroya ICHIKAWA
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Bottom-mounted instrumentation BWR Eddy current testing PWR Stress corrosion cracking
We confirmed the defect detection performance of the eddy current testing (ECT) system in order to inspect the bottom-Mounted instrumentation (BMI) nozzle in reactor pressure vessel. We developed the small size cross coil type ECT sensor that has the magnetic cores near the coils and the sensor driving unit based on the portable laser peening system. According to the experimental result that measured the relationship between the sensor inclined angle and defect detecting sensitivity on the convex surfa...
英字タイトル:
Development of Eddy Current Testing System for Bottom-Mounted Instrumentation Nozzle in Reactor Pressure Vessel
英字タイトル:
Development of Eddy Current Testing System for Bottom-Mounted Instrumentation Nozzle in Reactor Pressure Vessel
第15回
福島第一原子力発電所 第２／３号機 格納容器内部調査のための遠隔調査装置の開発と調査結果について
著者:
杉浦 鉄宰,清水 智得,小林 大治,坂本 直弥,久米 直人,畠山 誠,（東芝ESS/IRID）
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Decommissioning Fukushima Daiichi Investigation robot Melt-Down Accident
杉浦 鉄宰,清水 智得,小林 大治,坂本 直弥,久米 直人,畠山 誠,（東芝ESS/IRID）
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Decommissioning Fukushima Daiichi Investigation robot Melt-Down Accident
At the Fukushima Daiichi Nuclear Power Station, it is critical to (1) confirm the presence of fuel debris inside the PCV that could be melted fuel as a result of the hydrogen explosion followed by the accident; and (2) conduct in-depth investigations prior to decommissioning. However, the conditions inside the PCVs were unknown. Under this circumstance, International Research Institute for Nuclear decommissioning (IRID) and Toshiba ESS jointly developed devices that can access to the lower part of a PCV and...
英字タイトル:
Development of Remotely-Operated Devices for Investigation Inside Primary Containment Vessel (PCV) of Fukushima Daiichi Nuclear Power Station Unit 2 and 3 and Survey Results
英字タイトル:
Development of Remotely-Operated Devices for Investigation Inside Primary Containment Vessel (PCV) of Fukushima Daiichi Nuclear Power Station Unit 2 and 3 and Survey Results