Prediction of flow-induced excitation in a pipe conveying fluid-Reference-Cited by-同舟云学术

Prediction of flow-induced excitation in a pipe conveying fluid

Published:2005-02 Issue:5 Volume:235 Page:627-636
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Sinha Jyoti K.,Rao A. Rama,Sinha R.K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference14 articles.

1. ASME/ASNI O & M, 1990. ASME code on Operation and Maintenance of Nuclear Power Plants. Requirement for pre-operational and initial start-up vibration testing of Nuclear Power Plant Piping System, Part 3.

2. Flow-Induced Vibration;Blevins,1990

3. Flow-induced vibration in nuclear reactors: a review;Belvins;Prog. Nucl. Energy,1979

4. Modal Testing: Theory, Practice and Application;Ewins,2000

5. Practical Optimisation;Gill,1981

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