Published May 2012 | Version v1
Miscellaneous

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

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

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