Numerical solution of heat transfer process in a prismatic VHTR core accompanying bypass and cross flows-Reference-Cited by-同舟云学术

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Numerical solution of heat transfer process in a prismatic VHTR core accompanying bypass and cross flows

Published:2016-10 Issue: Volume:307 Page:275-283
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wang Li,Liu Qiusheng,Fukuda Katsuya

Funder

Japan Society for the Promotion of Science

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

Reference19 articles.

1. Ansys Inc., 2013. Ansys Fluent Theory Guide, Version 15.0.

2. Radiation effects in graphite and carbon-based materials;Burchell;MRS Bull.,1997

3. The Very High Temperature Reactor: A Technical Summary;Chapin,2004

4. General Atomics, 1996. Gas turbine-Modular Helium Reactor (GT-MHR) Conceptual Design Description Report. Doc. 910,720 Rev. 1.

5. Fundamentals of Heat and Mass Transfer;Incropera,2007

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