Preliminary Design of a Containment to Withstand Core Melt for a 1.100 MWe LWR System
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Date
1977
Authors
Advisors
Journal Title
Series/Report No.
J - Loading Conditions and Structural Analysis of Reactor Containment
J1 - Containment Concepts and Probabilistic Safety Assessment
SMiRT 4 - San Francisco, USA. 1977
J1 - Containment Concepts and Probabilistic Safety Assessment
SMiRT 4 - San Francisco, USA. 1977
Journal ISSN
Volume Title
Publisher
IASMiRT
