Experimental Development of Design Criterion to Limit Liquid Flow Induced Vibration in Nuclear Reactor Steam Generators

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Title: Experimental Development of Design Criterion to Limit Liquid Flow Induced Vibration in Nuclear Reactor Steam Generators
Author: D.J. Gorman; S. Mirza
Publisher: IASMiRT
Date: 1975
Series/Report No.: F - Structural Analysis of Reactor Core and Coolant Circuit Structures
F7 - Structural Analysis of Heat Exchangers
SMiRT 3 - London, UK. 1975
URI: http://www.lib.ncsu.edu/resolver/1840.20/28263


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