Computational fluid dynamics analysis of core bypass flow and crossflow in a prismatic very high temperature gas-cooled nuclear reactor based on a two-layer block model-Reference-Cited by-同舟云学术

Computational fluid dynamics analysis of core bypass flow and crossflow in a prismatic very high temperature gas-cooled nuclear reactor based on a two-layer block model

Published:2014-03 Issue: Volume:268 Page:64-76
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Wang Huhu,Dominguez-Ontiveros Elvis,Hassan Yassin A.

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

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4. Disturbance of the cooling gas distribution in HTGR fuel blocks due to bypass flow;Groehn,1980

5. Investigating leakage and bypass flows in an HTR using a CFD methodology;Janse van Rensburg;Nucl. Eng. Des.,2011

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