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 language | English (US) |
|---|---|
| State | Published - Jan 1 2003 |
| Event | 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003 - Cordoba, Spain Duration: May 4 2003 → May 7 2003 |
Other
| Other | 2nd International Congress on Advances in Nuclear Power Plants, ICAPP 2003 |
|---|---|
| Country | Spain |
| City | Cordoba |
| Period | 5/4/03 → 5/7/03 |
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All Science Journal Classification (ASJC) codes
- Geotechnical Engineering and Engineering Geology
Cite this
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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 conference › Paper
TY - CONF
T1 - Engineered safety features for in-vessel retention of large power reactors
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.
AU - Kim, S. B.
PY - 2003/1/1
Y1 - 2003/1/1
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.
AB - 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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M3 - Paper
ER -