Numerical simulation of fluid–structure interaction dynamics under seismic loadings between main and safety vessels in a sodium fast reactor-Reference-Cited by-同舟云学术

Numerical simulation of fluid–structure interaction dynamics under seismic loadings between main and safety vessels in a sodium fast reactor

Published:2012-12 Issue: Volume:253 Page:125-141
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Chellapandi P.,Chetal S.C.,Raj Baldev

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

Reference13 articles.

1. Seismic Resistance of FBR Components Influenced by Buckling;Akiyama,1997

2. Seismic Analysis of Safety Related Nuclear Structures and Commentary;ASCE,1998

3. ASME, 2004. Boiler and Pressure Vessel Code, Sec III, Div-1, Non-Mandatory Appendix-N: Dynamic Analysis Methods.

4. ASME, 2007a. Boiler & Pressure Vessel Code (2007), Sec. III Div. 1, Subsection NB, Class 1 Components, Rules for Construction of Nuclear Facility Components.

5. ASME, 2007b. Boiler & Pressure Vessel Code (2007), Sec. III Div. 1 – Appendices, Non-Mandatory Appendix F, Article F-1000, Rules for Evaluation of Service Loadings with Level D Service Limits.

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1. Influence of seismic isolation on the earthquake response of internal components in a fast reactor;Nuclear Engineering and Design;2023-11

2. Dynamic analysis of a partially-filled cylindrical–conical–cylindrical shell representing a pressure vessel;Thin-Walled Structures;2023-02

3. Vibration analysis of a system of partially-filled interconnected cylindrical shells representing a fast reactor;Journal of Fluids and Structures;2022-07

4. Deterministic and Probabilistic Evaluation of Seismic Loads on Reactor Pressure Vessel Internals Including Nonlinear Effects;Journal of Pressure Vessel Technology;2022-03-08

5. Implications of large scale sodium water reactions in an LMFBR;Nuclear Engineering and Design;2018-10