Development of a Technology to Investigate inside the Reactor Primary Containment Vessel (PCV). Site test 'Investigation B1' report on grating around the pedestal inside Unit 1 PCV. (Prompt Report of Inspection Commencement on April 10, 2015)

Published April 10, 2014 | Version v1

Miscellaneous Metadata-only

no abstract available

Availability note (English)

Available from Fukushima Nuclear Accident Archive https://f-archive.jaea.go.jp/dspace/handle/faa/160780?locale=eng

Country of Publication: Japan
Country of Input or Organization: Japan
INIS RN: 51122741
Subject category: S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator: Non-conventional Literature, No Abstract
Descriptors DEI: ACCIDENT MANAGEMENT; CAMERAS; CORIUM; DOSEMETERS; FLOORS; FUKUSHIMA ACCIDENT DATA; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; FUKUSHIMA-1 REACTOR; GUIDE TUBES; IMAGES; MELTDOWN; ON-SITE INSPECTION; PRESSURE VESSELS; REACTOR COMPONENTS; REMOTE CONTROL; ROBOTS; SUPPORTS; THERMOMETERS
Descriptors DEC: ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BWR TYPE REACTORS; CONTAINERS; CONTROL; DATASETS; DOCUMENT TYPES; ENRICHED URANIUM REACTORS; EQUIPMENT; FUKUSHIMA ACCIDENT ARCHIVE; INSPECTION; MANAGEMENT; MEASURING INSTRUMENTS; MECHANICAL STRUCTURES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Notes: Progress report files are available from Fukushima Nuclear Accident Archive, Japan; Nuclear Accidents Knowledge Taxonomy (NKMS, IAEA): 5-5-1 Radiation and engineering survey; 2-2-5 Containment system