Published March 2015
| Version v1
Report
Proposal of the concept of selection of accidents that release large amounts of radioactive substances in the high temperature engineering test reactor
- 1. Japan Atomic Energy Agency, Sector of Nuclear Science Research, Oarai Research and Development Center, Oarai, Ibaraki (Japan)
Description
In Position, construction and equipment of testing and research reactor to be subjected to the use standards for rules Article 53 (prevention of expansion of the accident to release a large amount of radioactive material) generation the frequency is a lower accident than design basis accident, when what is likely to release a large amount of radioactive material or radiation from the facility has occurred, and take the necessary measures in order to prevent the spread of the accident. There is provided a lower accident than frequency design basis accidents, for those that may release a large amount of radioactive material or radiation. (author)
Additional details
Publishing Information
- Imprint Title
- Report of workshop on operation, management and improvement of research reactors, Yayoi Research Group FY2014
- Imprint Pagination
- 112 p.
- Journal Page Range
- p. 11.1-11.6
- Report number
- UTNL-R--0489
Conference
- Title
- Workshop on operation, management and improvement of research reactors, Yayoi Research Group FY2014
- Dates
- 2 Mar 2015
- Place
- Tokai, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47053431
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; DESIGN BASIS ACCIDENTS; DOSE LIMITS; EARTHQUAKES; ECCS; EXCEPTIONAL NATURAL DISASTER; EXTERNAL ZONES; FAILURE MODE ANALYSIS; HTTR REACTOR; HYPOTHETICAL ACCIDENTS; LOSS OF COOLANT; OUTAGES; RADIOACTIVE MATERIALS; REACTOR ACCIDENT SIMULATION; SCRAM
- Descriptors DEC
- ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; NATURAL DISASTERS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SAFETY STANDARDS; SEISMIC EVENTS; SHUTDOWN; SIMULATION; STANDARDS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS
Optional Information
- Notes
- 3 figs., 1 tab.