A CFD Assessment of a Bypass Flow in a Cooled-Vessel Design of a Prismatic VHTR
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Due to higher operating temperatures, design of a reactor pressure vessel (RPV) is very important in Very High Temperature Reactors (VHTR). Recently KAERI has developed a cooled-vessel concept for a prismatic VHTR that allows the use of a SA-508/533 vessel as used in the commercial light-water reactors by maintaining the vessel temperature below its operating structural limit. A parametric study was conducted for the vessel cooling flow rate and the location of the riser holes in the reflector. Although the cooled-vessel design allows us to use the conventional reactor vessel, the bypass flow, one of the related issues, has not been evaluated. The purpose of this study is to assess how much bypass flow occurs due to routing the flow path into the graphite structure in the cooled-vessel design. A model to assess the bypass flow is developed by using the ANSYS CFX code. The analysis is performed to examine the effect of the gap size of the graphite blocks on the bypass flow. In addition, the effect of the block arrangement in a vertical direction is also investigated
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2008 spring meeting of the KNS
- Dates
- 29-30 May 2008
- Place
- Kyeongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 39109028
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- A CODES; BYPASSES; DESIGN; FLOW RATE; PRESSURE VESSELS; REACTOR VESSELS; VHTR REACTOR
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 2 refs, 6 figs