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Published October 2009 | Version v1
Miscellaneous

Natural Circulation Capability Assessment for Small-Medium Reactor

  • 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

Part of:
Transactions of the Korean Nuclear Society Autumn Meeting

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