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