Published October 2010 | Version v1
Miscellaneous

Safety Depressurization System Capability for High Pressure Core Melting Accidents in APR1400

  • 1. KHNP Co., Daejeon (Korea, Republic of)

Description

In the case of a high-pressure core melt-down accident, the released molten material from a reactor vessel can lead to increase the containment pressure and temperature by heat transfer via direct contact between the containment atmosphere and the dispersed molten material. This phenomenon is known as direct containment heating (DCH). High-pressure melt ejection (HPME) and DCH became severe accident (SA) safety issues in the 1980s. Many studies were performed in the USA to understand these events during the 1980s and 1990s. Currently, a reliable safety depressurization system (SDS) is required to prevent HPME/DCH events. A number of ALWRs such as EPR, APWR and AP1000 have been adopted SDS in their design. Especially, a dedicated SDS for severe accident mitigation is required in Europe. The APR1400 is designed with dedicated SDS for severe accidents in order to meet European requirements. In this paper, an evaluation of the SDS capacity is performed for high-pressure accidents of the APR1400 using MAAP4: The result can be expected to be technical basis for a serve accident management guidelines (SAMGs)

Part of:
Proceedings of the KNS 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
2010 autumn meeting of the KNS
Dates
21-22 Oct 2010
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
42085397
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCIDENTS; DEPRESSURIZATION; HEAT TRANSFER; MELTING; PWR TYPE REACTORS; REACTOR VESSELS; SAFETY
Descriptors DEC
CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs, 3 figs, 1 tab