Temperature transient analysis of gas circulator trip test using the HTTR
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
Safety demonstration test using the High Temperature Engineering Test Reactor (HTTR) are in progress to verify the inherent safety features, to improve the safety design and the technologies for High Temperature Gas-cooled Reactor (HTGRs). The coolant flow reduction test by tripping one or two out of three gas circulators is one of the safety demonstration test. The reactor power safely brings to a stable level without a reactor scram and the temperature transient of the reactor-core is very slow. Through the safety demonstration test, the two dimensional temperature analysis code (TAC-NC code) was improved. The results of this study can be applied to development for not only the commercial HTGRs but also the Very High Temperature Reactor (VHTR) such as one of the Generation IV reactors. This paper describes the validation of the TAC-NC code using the measured value of the test by tripping of one and two out of three gas circulators at 30% (9MW) performed in 2003. The TAC-NC code could evaluate accurately the temperature transient within 10% during the test. Also, it was confirmed that the temperature transient by tripping all gas circulators is very slow and that the HTGR has high inherent safety features. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 11 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36053641
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CIRCULATING SYSTEMS; FAILURES; HEAT TRANSFER; HTTR REACTOR; LOSS OF FLOW; REACTOR COOLING SYSTEMS; REACTOR SAFETY; T CODES; TEMPERATURE DISTRIBUTION; TRANSIENTS; VALIDATION; VHTR REACTOR
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TESTING; THERMAL REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name TUESDAY October 5, 2004, Paper ID N6P 220.pdf