Published May 2001 | Version v1
Miscellaneous

Numerical studies on penetration integrity of the KNGR lower pressure vessel in a severe accident

  • 1. KAERI, Taejon (Korea, Republic of)

Description

Numerical studies are conducted in parallel to experiments on penetration integrity of a lower pressure vessel in the Korean Next Generation Reactor(KNGR). KNGR-ICI-DRY experiments were performed two times without external vessel cooling. In this study experimental results on KNGR-ICI-DRY2 case was evaluated numerically using commercial software FLUENT and in-house code LILAC which has been developed at KAERI for a multi-dimensional analysis of melt pool in a pressure vessel. Natural convection and solidification of alumina melt are modeled in the numerical study. And conjugate heat transfer between the alumina melt and vessel are solved from the numerical results it is found that ICI nozzle directly contacted with alimina was melted and this melting heat affected heat transfer to lower vessel wall. The numerical and experimental analysis depict that the thermal load from 40 kg of alumina used in the KNGR-ICI-DRY2 case is not enough for failure of penetration integrity

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[11 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040376
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
EXPERIMENTAL DATA; HEAT TRANSFER; KAERI; NOZZLES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR ACCIDENTS
Descriptors DEC
ACCIDENTS; CONTAINERS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; KOREAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs, 11 figs