Feasibility experiments were performed for the assessment of improved In-Vessel Corium Retention (IVR) concepts using an internal engineered gap device and also a dual strategy of In/Ex-vessel cooling using the LAVA experimental facility. The internal engineered gap device made of carbon steel was installed inside the LAVA lower head vessel and it made a uniform gap with the vessel by 10 mm. In/Ex-vessel cooling in the dual strategy experiment was performed installing an external guide vessel outside the LAVA lower head vessel at a uniform gap of 25 mm. The LAVA lower head vessel was a hemispherical test vessel simulated with a 1/8 linear scale mock-up of the reactor vessel lower plenum with an inner diameter of 500 mm and thickness of 25 mm. In both of the tests, Al2O3 melt was delivered into about 50K subcooled water inside the lower head vessel under the elevated pressure. Temperatures of the internal engineered gap device and the lower head vessel were measured by K-type thermocouples embedded radially in the 3mm depth of the lower head vessel outer surface and in the 4mm depth of the internal engineered gap device, respectively. In the dual strategy experiment, the Ex-vessel cooling featured pool boiling in the gap between the lower head vessel and the external guide vessel. It could be found from the experimental results that the internal engineered gap device was intact and so the vessel experienced little thermal and mechanical attacks in the internal engineered gap device experiment. And also the vessel was effectively cooled via mutual boiling heat removal in- and ex-vessel in the dual strategy experiment. Compared with the previous LAVA experimental results performed for the investigation of the inherent in-vessel gap cooling, it could be confirmed that the Ex-vessel cooling measure was dominant over the In-vessel cooling measure in this study. It is concluded that the improved cooling measures using a internal engineered gap device and a dual strategy promote the cooling characteristics of the lower head vessel and so enhance the integrity of the vessel in the end.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Experimental Study on the Improved In-Vessel Corium Retention Concepts for the Severe Accident Management
K. H. Kang,
K. H. Kang
Korea Atomic Energy Research Institute, Taejon, Korea
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R. J. Park,
R. J. Park
Korea Atomic Energy Research Institute, Taejon, Korea
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K. M. Koo,
K. M. Koo
Korea Atomic Energy Research Institute, Taejon, Korea
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S. B. Kim,
S. B. Kim
Korea Atomic Energy Research Institute, Taejon, Korea
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H. D. Kim
H. D. Kim
Korea Atomic Energy Research Institute, Taejon, Korea
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K. H. Kang
Korea Atomic Energy Research Institute, Taejon, Korea
R. J. Park
Korea Atomic Energy Research Institute, Taejon, Korea
K. M. Koo
Korea Atomic Energy Research Institute, Taejon, Korea
S. B. Kim
Korea Atomic Energy Research Institute, Taejon, Korea
H. D. Kim
Korea Atomic Energy Research Institute, Taejon, Korea
Paper No:
ICONE10-22176, pp. 213-220; 8 pages
Published Online:
March 4, 2009
Citation
Kang, KH, Park, RJ, Koo, KM, Kim, SB, & Kim, HD. "Experimental Study on the Improved In-Vessel Corium Retention Concepts for the Severe Accident Management." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 213-220. ASME. https://doi.org/10.1115/ICONE10-22176
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