Numerical Analysis on the Scaled Air Cooled RCCS Test Facility
- 1. Korea Atomic Energy Research Institute, Daedeok daero 989 11, Yuseong Gu, Daejeon (Korea, Republic of)
Description
The Korea Atomic Energy Research Institute (KAERI) has been studying a prismatic type of High Temperature Gas cooled Reactor (HTGR) as a generation IV reactor. An HTGR may remove a residual heat without a supply of electricity under a severe accident by a Reactor Cavity Cooling System (RCCS). The RCCS uses only natural circulation of air to remove heat transferred by the radiation from the reactor pressure vessel. KAERI has been testing a scale downed RCCS to investigate the feasibility of a passive heat removal system. As the size is reduced, the non dimensional parameters are applied to maintain similarity. After the test, a Computational Fluid Dynamic (CFD) analysis is conducted to design the RCCS system. In the present study, the different types of turbulence models are applied to investigate the flow characteristics in the riser duct based on the test condition. (author)
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Additional details
Publishing Information
- Imprint Title
- 9th International Conference on High Temperature Reactor Technology (HTR2018)
- Imprint Pagination
- vp.
- Journal Page Range
- 4 p.
- Report number
- INIS-PL--23M0001
Conference
- Title
- 9. International Conference on High Temperature Reactor Technology
- Acronym
- HTR2018
- Dates
- 8-10 Oct 2018
- Place
- Warsaw (Poland)
INIS
- Country of Publication
- Poland
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54061961
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AIR; COOLING SYSTEMS; DESIGN; FEDERAL REPUBLIC OF GERMANY; FLUID MECHANICS; FORSCHUNGSZENTRUM JUELICH; HTGR TYPE REACTORS; NUCLEAR ENERGY; PRESSURE VESSELS; SEVERE ACCIDENTS; TEMPERATURE RANGE 0400-1000 K; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CONTAINERS; DEVELOPED COUNTRIES; ENERGY; ENERGY SYSTEMS; EUROPE; FLUIDS; GAS COOLED REACTORS; GASES; GERMAN FR ORGANIZATIONS; GRAPHITE MODERATED REACTORS; MECHANICS; NATIONAL ORGANIZATIONS; REACTORS; TEMPERATURE RANGE; WESTERN EUROPE
Optional Information
- Notes
- Document from Juelich Preservation Project; 6 refs., 6 figs., 1 tab.
- Secondary number(s)
- HTR2018--59