Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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MULTIPHASE FLOW IN EX-VESSEL COOLABILITY: DEVELOPMENT OF AN INNOVATIVE CONCEPT

  • CORRADINI MICHAEL L. (University of Wisconsin)
  • Published : 2006.02.01
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Abstract

The interaction and mixing of high-temperature melt and water is the important technical issue in the safety assessment of water-cooled reactors to achieve ultimate core coolability. For specific advanced light water reactor (ALWR) designs, deliberate mixing of the core-melt and water is being considered as a mitigative measure, to assure ex-vessel core coolability. The paper provides the background of past experiments as well as key fundamentals that are needed for melt-water interfacial transport phenomena, thus enabling the development of innovative safety technologies for advanced LWRs that will assure ex-vessel core coolability.

Keywords

References

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