第15回
3Dアズビルドレーザ計測を利用したライニング配管の製作・据付精度向上
著者:
川村 国治,井上 勝,川端 カイオ,(三菱重工)
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Due to the high degree of required dimensional accuracy in its manufacturing, repairing of lining pipes with flanges requires a long installation period. With the conventional method, we have to wait more than three weeks to start lining installation after the start of onsite construction, because pipe dimensions are determined onsite then lining installation is conducted at shop. It causes prolongation of the onsite installation period. Therefore, we have tried to improve the dimensional accuracy in its ma...
英字タイトル:
Improvement in Manufacturing and Installation Accuracy of Lining Piping by Application of 3D As-built Laser Measurement
第15回
PRAから想定される検査対象設備候補の検討
著者:
高橋 浩道,高田 洋祐,長谷川 悠,田中 太,(三菱重工)
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MHI (Mitsubishi Heavy Industry) is focusing on selection SSCs with using risk importance for new inspection system. In this paper, a trial use of new inspection guidance for selection SSCs is described....
英字タイトル:
A trial use of New Inspection Guidance for Selection SSCs with using Risk importance
第16回
PWRプラントにおける最近の被ばく低減に関する取り組みについて
著者:
山﨑 慎吾,前田 哲宏,石原 伸夫,(三菱重工),長嶺 邦孝,(ニュークリアデベロップメント)
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The zinc injection has been applied to the Japanese PWR plants for reduction of dose rate of main equipment into the middle of the 2000s. As a result, the dose rate of main equipment was reduced about 40%. In addition to the zinc injection, new measure to reduce of dose rate is demanded. We note the primary water radiation changes significantly, even when water quality and a plant operation parameter are similar value. It is introduced that the approach for identifying the unexplained radiation factor....
英字タイトル:
The approach about the reduction of dose rate in Japanese PWR Plants
第16回
PWR廃止措置における炉内サンプリング工事について
著者:
永田 亮,新田 義一,橋本 達矢,池谷 俊志,森川 玲於奈,鬼塚 博徳,南山 彰男,野田 雅紀,(三菱重工)
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Mihama Unit 1 & 2 are the first decommissioned nuclear power plants in the Japanese PWR (Pressurized Water Reactor). Internal reactor vessel sampling in PWR has never been conducted in Japan before. Mihama Unit 1 & 2 is the first one in the Japanese PWR. Usually, radioactive concentration on nuclear power plant is estimated based on operation history. Decommissioned nuclear power plants are demanded verification between estimation of radioactive concentration and measured result. This dissertation is descri...
英字タイトル:
The nation’s sampling of internal reactor vessel on PWR decommissioning
第16回
コンクリート建屋のレーザ切断工法
著者:
赤羽 崇,呉屋 真之,森 宏樹,奥田 剛久,下鍋 典昭,(三菱重工),井上 隆司,中越 淳郎,(鹿島建設)
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The demolition technics of the thick broad concrete wall of atomic power building of a Fukushima Daiichi nuclear power plant by the remote laser cutting have been developed. In this time, the outline about laser cutting technology of a concrete wall, the demolition method and equipment is introduced....
英字タイトル:
The laser cutting construction method of a concrete building
第16回
ソフトセンサ(仮想計測)を用いたプラント水質監視に関する取り組み
著者:
澤津橋 徹哉,梶 伸之介,嬉野 絢子,松原 龍一,松澤 寛,(三菱重工),船津 公人,(東京大)
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On a power plant, the water quality of system water needs to be properly monitored and controlled. On this study proposes a monitoring method for the concentration of Chloride, one of the main impurities dissolved in feed water of a power plant. The proposed method is based on soft sensor, and variable selection through GAVDS contributes the predictive models to higher prediction accuracy....
第15回
バレルフォーマボルト、炉心そう等のIASCC保全に関する取り組み
著者:
最上 雄一,和地 永嗣,(三菱重工),池田 惇 ,(関西電力),関 弘明,(JANSI)
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Core barrel is a cylindrical support structure in reactor internals in PWR (Pressurized Water Reactor) plants and a baffle-former assembly and fuel assemblies are placed in it. Barrel former bolts fasten a baffle-former assembly to Core barrel. Core barrel and Barrel former bolts are exposed to relatively high neutron irradiation due to their proximity to fuel assemblies. In order to properly manage the structural integrity of these parts against the degradation caused by neutron irradiation, inspection and...
英字タイトル:
IASCC maintenance activities on Barrel Former Bolts and Core Barrel
第16回
プラント向けエッジ側状態監視処理システムの開発
著者:
中重 佑一,鉄谷 祐二,河合 佑紀,(三菱重工)
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In this paper, we propose a remote monitoring system for field instruments in plant operation using SMEc, which combines a camera with deep learning. By the needle position estimation logic, a recognition rate of 99% or more could be obtained within the target accuracy of 1 scale error. It was also confirmed from the response evaluation test that the dynamic behavior had sufficient responsiveness. Therefore, we believe that the introduction of SMEc has given us the prospect of realizing a system capable of ...
英字タイトル:
Development of Site Parameter Monitoring System with Edge Computer
第15回
レーザーガウジング除染工法に関する実用化研究成果
著者:
橋川 雄樹,(原子力サービスエンジニアリング),奥田 剛久,吉田 和弘,本田 翔也,(三菱重工)
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原子炉の保守・改造及び廃止措置時に発生する放射性廃棄物量低減のため、放射能レベル区分ダウング レードやクリアランスレベル(汚染レベルを低減させ、取扱いを容易にする)を目的とし、ラインレーザを用いたガウジング除染工法の開発を進めている。ここでは、PWR プラントの実汚染サンプルを用いた除染性能評価試験(Hot 試験)の成果について報告する。...
英字タイトル:
Development of Practical Realization for Laser-Gouging Decontamination Method
第16回
保全内容の変更判断をバックアップする数理手法の適用状況調査
著者:
堂﨑 浩二,(日本原電),行則 茂,(東芝ESS),高屋 茂,(JAEA),和地 永嗣,(三菱重工),青木 孝行,(東北大)
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It is important for maintenance of nuclear power station facilities in the future to promote mathematical techniques which support judgement to modify maintenance practices, such as maintenance tasks, maintenance implementation timing, and so on. Mathematical Maintenance Working Group, which has been established by Maintenance Standardization Committee since July 6, 2018, is investigating application examples of such mathematical techniques in maintenance planning as influence evaluation of changing maint...
英字タイトル:
Investigation on application examples of mathematical techniques to support judgement to modify maintenance practices