Published 2004 | Version v1
Miscellaneous

Assessment of in-vessel retention capability for APR1400

Creators

  • 1. Korea Hydraulic and Nuclear Power Company, Taejon (Korea, Republic of)

Description

The effectiveness of the external cooling of RPV strategy has been examined. For the key scenarios, MAAP code is used to derive the boundary condition for this investigation. Using MELTTHERM code, we examined the thermal margin for these scenarios. We found that there is enough thermal margin with the ULPU III CHF data. The effect of in-vessel injection with the external cooling of RPV is also examined. For the LBLOCA scenario, the heat flux ratio is 0.66 with the in-vessel injection. This translates into the thermal margin of 34%. For APR1400, the external cooling of RPV is a very effective severe accident management strategy in retaining corium in-vessel

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[9 p.]

Conference

Title
2004 spring meeting of the KNS
Dates
27-28 May 2004
Place
Gyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
35100410
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CORIUM; CRITICAL HEAT FLUX; INJECTION; LOSS OF COOLANT; M CODES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR VESSELS; RETENTION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; HEAT FLUX; INTAKE; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
12 refs, 4 figs, 2 tabs