An Assessment of Steam-Explosion-Induced Containment Failure. Part II: Premixing Limits
Author:
Affiliation:
1. University of California, Department of Chemical and Nuclear Engineering, Santa Barbara, California 93106
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE87-A23513
Reference10 articles.
1. An Assessment of Steam-Explosion-Induced Containment Failure. Part I: Probabilistic Aspects
2. An Assessment of Steam-Explosion-Induced Containment Failure. Part III: Expansion and Energy Partition
3. Steam Explosion Review Group, “A Review of Current Understanding of the Potential for Containment Failure Arising from In-Vessel Steam Explosions,” NUREG-1116, U.S. Nuclear Regulatory Commission (Feb. 1985).
4. An assessment of Class-9 (core-melt) accidents for PWR dry-containment systems
5. Mixing of Molten Core Material and Water
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