Published April 13, 2014
| Version v1
Miscellaneous
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 [For April 10]
Description
no abstract available
Availability note (English)
Available from Fukushima Nuclear Accident Archive https://f-archive.jaea.go.jp/dspace/handle/faa/160781?locale=engAdditional details
Additional titles
- Augmented title (English)
- Handouts at press conference on 2014-04-13
Identifiers
Publishing Information
- Imprint Pagination
- [html]
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51122742
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Non-conventional Literature, No Abstract
- Descriptors DEI
- ACCIDENT MANAGEMENT; CAMERAS; CORIUM; DOSEMETERS; ERRORS; FUKUSHIMA ACCIDENT DATA; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; FUKUSHIMA-1 REACTOR; GUIDE TUBES; IMAGES; MELTDOWN; MOCKUP; ON-SITE INSPECTION; PRESSURE VESSELS; REACTOR COMPONENTS; REMOTE CONTROL; ROBOTS; SV PER HOUR RANGE; TEMPERATURE RANGE 0273-0400 K; 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; POWER REACTORS; RADIATION DOSE RATE RANGES; REACTOR ACCIDENTS; REACTOR SITES; REACTORS; SEVERE ACCIDENTS; STRUCTURAL MODELS; TEMPERATURE RANGE; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- 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; Numerical data flagging: Survey data; Onsite; Dose rates; Temperatures