Development of a technology to investigate inside the Reactor Primary Containment Vessel (PCV); Site test "Investigation B1" on grating around the pedestal inside Unit 1 PCV [Prompt report for April 15, 2015]

タイトル	Development of a technology to investigate inside the Reactor Primary Containment Vessel (PCV); Site test "Investigation B1" on grating around the pedestal inside Unit 1 PCV [Prompt report for April 15, 2015]
情報提供機関	International Research Institute for Nuclear Decommissioning
掲載日	2015-04-16
言語	eng
ページ数	6p.
種別	presentation
ファイル形式	PDF
分類	5-5-1 放射線と工学サーベイ
分類	5-5-2 破損燃料廃止措置プログラム
分類	5-4 緊急事態用ロボット工学
内容	REACTOR DECOMMISSIONING, REMOTE HANDLING EQUIPMENT, CONTAINMENT SHELLS, CORIUM, fuel debris, Fukushima Daiichi Nuclear Power Station Unit 1, SURVEY, DOSE RATES, FIELD TESTS
情報源	保存されたウェブページへ
上位階層ページタイトル	Survey Device (Shape-changing Robot) Deployed to Inspect Interior of Primary Containment Vessel (PCV)
関連するコンテンツ	Development of a technology to investigate inside the Reactor Primary Containment Vessel (PCV) Status of (first) survey device Confirmation of access route to CRD rail Footage from on-board camera (1) (Main Camera) (16.2Sv/h 19.6℃) Footage from on-board camera (2) (Main Camera) (3.8Sv/h 20.4℃)
URI	https://f-archive.jaea.go.jp/dspace/handle/faa/97681
WARP保存日	2015-07-11

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