和地 永嗣
著者に関連した記事は3件です。
更新情報
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）
発刊日:
公開日:
キーワードタグ:
Barrel former bolts Core barrel Guideline IASCC Maintenance Reactor Internals
最上 雄一,和地 永嗣,（三菱重工）,池田 惇 ,（関西電力）,関 弘明,（JANSI）
発刊日:
公開日:
キーワードタグ:
Barrel former bolts Core barrel Guideline IASCC Maintenance Reactor Internals
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
英字タイトル:
IASCC maintenance activities on Barrel Former Bolts and Core Barrel
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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公開日:
キーワードタグ:
Bayesian Statistics Load and Resistance Factor Design Maintenance Standardization
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）
発刊日:
公開日:
キーワードタグ:
Bayesian Statistics Load and Resistance Factor Design Maintenance Standardization
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
英字タイトル:
Investigation on application examples of mathematical techniques to support judgement to modify maintenance practices
第17回
原子炉恒久停止から廃止措置までのリスクについて
著者:
田中 太,和地 永嗣,（三菱重工）
発刊日:
公開日:
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Decommissioning Risk Assessment Safety Assessment Spent fuel accident
田中 太,和地 永嗣,（三菱重工）
発刊日:
公開日:
キーワードタグ:
Decommissioning Risk Assessment Safety Assessment Spent fuel accident
For the planning of decommissioning and the establishment of appropriate safety control during its activity, risk assessment to understand the potential accident scenarios during decommissioning is essential. The decommissioning phase following permanent shutdown involves a complex process such as dismantling of equipment and facilities, demolition of building and structures. The decay heat and management of spent fuels also change by time during decommission. In comparison to nuclear power plants at operat...
英字タイトル:
Nuclear power plant risk after permanent shutdown to decommissioning
英字タイトル:
Nuclear power plant risk after permanent shutdown to decommissioning