Engineered safety features for in-vessel retention of large power reactors

K. Y. Suh, Y. H. Kim, S. D. Lee, C. S. Kim, J. L. Rempe, Fan-bill B. Cheung, S. B. Kim

Research output: Contribution to conferencePaper

5 Citations (Scopus)

Abstract

In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. However, it is not clear that currently-proposed external reactor vessel cooling (ERVC) could provide sufficient heat removal for higher power reactors. A United States (U.S.)-Korean International Nuclear Energy Research Initiative (INERI) project has been initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) will determine if IVR is feasible for reactors up to 1500 MWe. This paper summarizes results from the first year of this three year project.

Original languageEnglish (US)
StatePublished - Jan 1 2003
Event2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003 - Cordoba, Spain
Duration: May 4 2003May 7 2003

Other

Other2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003
CountrySpain
CityCordoba
Period5/4/035/7/03

Fingerprint

Accidents
vessel
safety
Nuclear energy
Cooling
accident
Light water reactors
Nuclear power plants
Molten materials
cooling
containment
nuclear power plant
reactor
melt
engineering
energy
water
material
project
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Geotechnical Engineering and Engineering Geology

Cite this

Suh, K. Y., Kim, Y. H., Lee, S. D., Kim, C. S., Rempe, J. L., Cheung, F. B., & Kim, S. B. (2003). Engineered safety features for in-vessel retention of large power reactors. Paper presented at 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003, Cordoba, Spain.
Suh, K. Y. ; Kim, Y. H. ; Lee, S. D. ; Kim, C. S. ; Rempe, J. L. ; Cheung, Fan-bill B. ; Kim, S. B. / Engineered safety features for in-vessel retention of large power reactors. Paper presented at 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003, Cordoba, Spain.
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Suh, KY, Kim, YH, Lee, SD, Kim, CS, Rempe, JL, Cheung, FB & Kim, SB 2003, 'Engineered safety features for in-vessel retention of large power reactors' Paper presented at 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003, Cordoba, Spain, 5/4/03 - 5/7/03, .

Engineered safety features for in-vessel retention of large power reactors. / Suh, K. Y.; Kim, Y. H.; Lee, S. D.; Kim, C. S.; Rempe, J. L.; Cheung, Fan-bill B.; Kim, S. B.

2003. Paper presented at 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003, Cordoba, Spain.

Research output: Contribution to conferencePaper

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AU - Suh, K. Y.

AU - Kim, Y. H.

AU - Lee, S. D.

AU - Kim, C. S.

AU - Rempe, J. L.

AU - Cheung, Fan-bill B.

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N2 - In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. However, it is not clear that currently-proposed external reactor vessel cooling (ERVC) could provide sufficient heat removal for higher power reactors. A United States (U.S.)-Korean International Nuclear Energy Research Initiative (INERI) project has been initiated in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) will determine if IVR is feasible for reactors up to 1500 MWe. This paper summarizes results from the first year of this three year project.

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Suh KY, Kim YH, Lee SD, Kim CS, Rempe JL, Cheung FB et al. Engineered safety features for in-vessel retention of large power reactors. 2003. Paper presented at 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003, Cordoba, Spain.