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Application of containment codes to LMFBRs in the united states

Authors
Journal
Nuclear Engineering and Design
0029-5493
Publisher
Elsevier
Publication Date
Volume
42
Issue
1
Identifiers
DOI: 10.1016/0029-5493(77)90061-9

Abstract

Abstract This paper describes the application of containment codes to predict the response of the fast reactor containment and the primary piping loops to HCDAs. Five sample problems are given to illustrate their applications. The first problem deals with the response of the primary containment to an HCDA. The second problem deals with the coolant flow in the reactor lower plenum. The third problem concerns sodium spillage and slug impact. The fourth problem deals with the response of a piping loop. The fifth problem analyzes the response of a reactor head closure. Application of codes in parametric studies and comparison of code predictions with experiments are also discussed.

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