New test plan about safety features of HTGR by using HTTR in JAEA
Creators
Description
Japan Atomic Energy Agency (JAEA) has High Temperature Engineering Test Reactor (HTTR) which is 30MW test reactor of HTGR. Although the HTTR was not operated after the Fukushima Daiichi accident in 2011, it restarted operation in July 2021. The HTTR can be used to carry out various tests about safety features of HTGR. In 2010, safety demonstration test about a loss of forced cooling (LOFC) condition was carried out under a framework of OECD/NEA. Two LOFC tests with different conditions will be done in early 2022. The LOFC project is an international joint project. After the LOFC, JAEA is planning to launch a new test project. Test theme concerning Xe build-up/decay behavior after reactor scram is one of the attractive new test themes, but not limited to this. This paper presents possible test themes by using the HTTR. JAEA has room to discuss possible new themes with expecting foreign partners to launch an international joint project. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs. Book of Abstracts
- Imprint Pagination
- 146 p.
- Journal Page Range
- p. 32
- Report number
- IAEA-CN--308
Conference
- Title
- Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Acronym
- International Conference on Topical Issues in Nuclear Installation Safety
- Dates
- 18-21 Oct 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004863
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DECAY; HTTR REACTOR; NUCLEAR ENERGY; PLANNING; REACTOR ACCIDENTS; REACTOR OPERATION; REACTOR SAFETY; SCRAM; TEST REACTORS
- Descriptors DEC
- ACCIDENTS; ENERGY; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; OPERATION; REACTOR LIFE CYCLE; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SHUTDOWN; TEST FACILITIES
Optional Information
- Secondary number(s)
- IAEA-CN--308-59