Study on the flow distribution in prismatic VHTR core with a multi-block experiment and CFD analysis-Reference-Cited by-同舟云学术

Study on the flow distribution in prismatic VHTR core with a multi-block experiment and CFD analysis

Published:2011-12 Issue:12 Volume:241 Page:5174-5182
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Yoon Su-Jong,Jin Chang-Yong,Lee Jeong-Hun,Kim Min-Hwan,Park Goon-Cherl

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

Reference16 articles.

1. CFX-12 Solver Theory;ANSYS Canada Ltd.,2010

2. The effect of neutron irradiation on the structure and properties of carbon–carbon composite materials;Burchell;Journal of Nuclear Materials,1994

3. GAMBIT 2.3 User's Guide;FLUENT Inc.,2006

4. Handbook of Hydraulic Resistance;Idelchik,1996

5. Introduction to Heat Transfer;Incropera,1996

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