Published October 2013 | Version v1
Miscellaneous

Severe Accident Mitigation by using Core Catcher applicable for Korea standard nuclear power plant

  • 1. Kyung Hee Univ., Yongin (Korea, Republic of)

Description

Nuclear power plants have been designed and operated in order to prevent severe accident because of their risk that contains tremendous radioactive materials that are potentially hazardous. Moreover, the government requested the nuclear industry to implement a severe accident management strategy for existing reactors to mitigate the risk of potential severe accidents. However, Korea standard nuclear power plant(APR-1400 and OPR-1000) are much more vulnerable for severe accident management than that of developed countries. Due to the design feature of reactor cavity in Korea standard nuclear power plant, inequable and serious Molten Core-Concrete Interaction(MCCI) may cause considerable safety problem to the reactor containment liner. At worst, it brings the release of radioactive materials to the environment. This accident applies to the fourth level of defense in depth(IAEA 1996), 'severe accident'. This study proposes and designs the 'slope' to secure reactor containment liner integrity when the corium spreads out from the destroyed reactor vessel to the reactor cavity due to the core melting accident. For this, make the initial corium distribution evenly exploit the 'slope' on the basis of the study of Ex-vessel corium behavior to prevent inequable and serious MCCI, in order to mitigate severe accident. The viscosity has a dominant position in the calculation. According to the result, the spread out distance on the slope is 10.7146841m, considering the rough surface of the concrete(slope) and margin of reactor cavity end(under 11m). Easy to design, production and economic feasibility are the advantage of the designed slope in this study. However, the slope design may unsuitable when the sequences of the accidents did not satisfy the assumptions as mentioned. Despite of those disadvantages, the slope will show a great performance to mitigate the severe accident. As mentioned in assumption, the corium releasing time property was conservatively calculated(fastest). So, applying the slope on the reactor cavity can mitigate the accident any more than not, even accident development unsuspected sequences(flow, releasing time, vessel failure position)

Part of:
Proceedings of the KNS Fall meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS Fall meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2013 Fall meeting of the KNS
Dates
23-25 Oct 2013
Place
Kyungju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
45082398
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; CORIUM; DESIGN; PWR TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR VESSELS; VISCOSITY
Descriptors DEC
ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs, 3 figs, 2 tabs