Analysis of External Cooling of the Reactor Vessel During Severe Accidents
Author:
Affiliation:
1. Korea Atomic Energy Research Institute, P.O. Box 105 Yusong Post Office, Taejon, 305-600, Korea
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT02-A3279
Reference15 articles.
1. In-vessel coolability and retention of a core melt
2. The coolability limits of a reactor pressure vessel lower head
3. A hydrodynamic critical heat flux model for saturated pool boiling on a downward facing curved heating surface
4. An experimental study of saturated pool boiling from downward facing and inclined surfaces
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