Slug Impact Loading on the Vessel Head during a Postulated In-Vessel Steam Explosion in Pressurized Water Reactors–Assessments and Discussion of the Investigation Strategy
Author:
Affiliation:
1. Forschungszentrum Karlsruhe Institut für Reaktorsicherheit, Postfach 3640, D-76021 Karlsruhe
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/NT95-A15867
Reference28 articles.
1. Research and Development to Improve Containment for the Next Generation of Pressurised Water Reactor Plants
2. Severe Accident Containment Loads and Possible Design Concepts of Future Large Pressurized Water Reactors
3. Can the acceptance of nuclear reactors be raised by a simpler, more transparent safety concept employing improved containments?
4. An Assessment of Steam-Explosion-Induced Containment Failure. Part IV: Impact Mechanics, Dissipation, and Vessel Head Failure
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