Effect of coolant in penetration on integrity of the reactor vessel during a severe accident
- 1. KAERI, Taejon (Korea, Republic of)
Description
When the melted core material relocated to lower plenum during a severe accident in the nuclear power plants, the effect of coolant in the annulus between the ICI (In-Core Instrumentation) nozzle and the thimble tube on integrity of the pressure vessel has been estimated in this experimental study. Two tests in conditions with and without coolant in the annulus have been performed using alumina melt 40 kg as a simulant. The test results have shown that much melts ejected to the outside through the penetration in conditon without coolant in the annulus. However, small melt ejected to the outside through the penetration in the condition with coolant in the annulus, because the coolant prevent the melt from ejection through penetration. It is confirmed from the test results that the coolant in the annulus between the ICI nozzle and the thimble tube is very effective on the maintenance of the reactor vessel 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
- [12 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
- 33040418
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COOLANTS; NOZZLES; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR CORES; REACTOR VESSELS; TUBES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 7 refs, 7 figs, 2 tabs