Safety Issues of VHTR RCCS Design
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
The concept of passive safety is emphasized in VHTR (Very High Temperature Reactor) to accomplish the enhanced safety goal of future reactors compared to the reactors of previous generation. The Reactor Cavity Cooling System (RCCS) is the passive safety system in VHTR designed to remove the residual and decay heat. Large thermal margin, low power density and core configuration with large heat transfer surface in VHTR make passive cooling effective. In addition, RCCS in VHTR is the only safety-related system which should have a high reliability. Therefore, it is important to study the design characteristics of RCCS and derive safety issues to assure the passive safety of VHTR. In this paper, several safety issues related with RCCS in VHTR were identified and reviewed
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
- 2012 spring meeting of the KNS
- Dates
- 16-18 May 2012
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43073302
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; DESIGN; HEAT TRANSFER; RELIABILITY; SAFETY; VHTR REACTOR
- Descriptors DEC
- ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTORS; REMOVAL; RESEARCH AND TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 3 refs, 1 fig