Steam explosion may occur in nuclear power plants by fuel-coolant interactions when the external reactor vessel cooling strategy is failed. This phenomenon can cause shock wave that endangers surrounding reactor cavity wall due to resulting dynamic effects. Even though extensive researches have been performed to predict influences of the steam explosion, due to complexity of physical phenomena and thermal-hydraulic conditions, it is remained as one of possible hazards. The object of this study is to examine characteristics of reactor cavity and nuclear components under representative steam explosion conditions. In this context, an assembled finite element mesh was generated and evaluated by the trinitrotoluene model. As a result, stresses, strains and displacements of the reactor cavity and nuclear components were calculated. Subsequently, crack evaluation of reinforced concrete was performed and their results were discussed.
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ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5041-1
PROCEEDINGS PAPER
Reactor Cavity Analysis Under Steam Explosive Conditions by TNT Model
Seung-Huyn Kim,
Seung-Huyn Kim
Kyung Hee University, Yongin-si, Korea
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Yoon-Suk Chang,
Yoon-Suk Chang
Kyung Hee University, Yongin-si, Korea
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Yong-Jin Cho
Yong-Jin Cho
Korea Institute of Nuclear Safety, Daejeon, Korea
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Seung-Huyn Kim
Kyung Hee University, Yongin-si, Korea
Yoon-Suk Chang
Kyung Hee University, Yongin-si, Korea
Yong-Jin Cho
Korea Institute of Nuclear Safety, Daejeon, Korea
Paper No:
PVP2016-63224, V005T05A020; 4 pages
Published Online:
December 1, 2016
Citation
Kim, S, Chang, Y, & Cho, Y. "Reactor Cavity Analysis Under Steam Explosive Conditions by TNT Model." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop. Vancouver, British Columbia, Canada. July 17–21, 2016. V005T05A020. ASME. https://doi.org/10.1115/PVP2016-63224
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