Natural Circulation Capability Assessment for Small-Medium Reactor
Creators
- 1. Hanyang University, Seoul (Korea, Republic of)
- 2. POSTECH, Pohang (Korea, Republic of)
Description
Small-medium reactors have been highly evaluated to have more safe characteristics than those of large reactors. In addition, it could be used for a variety of purposes, such as small-scale power production in mountainous or island area, seawater desalination, regional heating system, or large ships promotion power source. Various countries recently have substantiated the small-medium reactors . AST-500 (Russia), NHR-5 and NHR-200 (China), GHR (Germany), SMART (Korea). Since SMART (System-integrated Modular Advanced ReacTor) is integral type contrarily to the original reactors, it contains primary systems including a core, main coolant pumps, steam generators and a pressurizer within a reactor pressure vessel. Accordingly, it can exclude LBLOCA(Large Break Loss Of Coolant Accident) which is primary DBA(Design Basis Accident) of separated reactors. For a higher safety, we are designing a small sized reactor, REX-10(Regional Energy Reactor - 10 MWth), which uses a natural circulation system. In This study, to evaluate thermal-hydraulics of REX-10, we built experiment facility using the scaling law by Ishii
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2009 autumn meeting of the KNS
- Dates
- 29-30 Oct 2009
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 41027076
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- LOSS OF COOLANT; NATURAL CONVECTION; POWER GENERATION; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR VESSELS; SAFETY; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONVECTION; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MASS TRANSFER; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs, 1 fig, 2 tabs