Moderator temperature prediction under 35% RIH break LOCA with LOECC in CANDU-6
Creators
- 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)
- 2. Handong Global University, Kyungbuk (Korea, Republic of)
Description
In CANDU-6 reactor, the fuel channel integrity depends on the coolability of the moderator as the ultimate heat sink in a transient condition such as a loss of coolant accident (LOCA) with a coincidental loss of emergency core cooling (LOECC), as well as a normal operating condition. This paper presents the assessments for real CANDU-6 of the normal operating condition and the transient condition, using a general purpose CFD code. A real Calandria vessel of CANDU-6 with 380 fuel channels was simulated and a series of calculations with optimized numerical scheme were carried out to analyze the fluid flow and temperature distributions. Under the normal operating condition, mixed type flow pattern was predicted and the three flow patterns were observed according to inlet flow rate and heat load. The transient condition of a LOCA with a coincidental LOECC was also investigated with the same calculation schemes. Detailed investigations are performed for thermal hydraulic characteristics in terms of the velocity and temperatures of moderator. (author)
Additional details
Publishing Information
- Imprint Title
- NTHAS4: Proceedings of the 4th Japan-Korea symposium on nuclear thermal hydraulics and safety
- Imprint Pagination
- 576 p.
- Journal Page Range
- p. 503-505
Conference
- Title
- 4. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Dates
- 28 Nov - 1 Dec 2004
- Place
- Sapporo, Hokkaido (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 37000558
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; C CODES; CALANDRIAS; CANDU TYPE REACTORS; COMPUTERIZED SIMULATION; DRYOUT; ECCS; FLUID FLOW; FUEL INTEGRITY; HEAT TRANSFER; LOSS OF COOLANT; MODERATORS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SIMULATION; THERMAL REACTORS
Optional Information
- Notes
- Also available on CD-ROM, data in PDF format; 000088.pdf; 3 refs., 4 figs.