Experimental study of core bypass flow in a prismatic VHTR based on a two-layer block model-Reference-Cited by-同舟云学术

Experimental study of core bypass flow in a prismatic VHTR based on a two-layer block model

Published:2016-09 Issue: Volume:306 Page:98-107
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

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

Funder

Idaho National Laboratory

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

Reference12 articles.

1. Disturbance of the Cooling Gas Distribution in HTGR Fuel Blocks due to Bypass Flow;Groehn,1980

2. Turbulence;Hinze,1975

3. Bypass flow computations using a one-twelfth symmetric sector for normal operation in a 350 MWth prismatic VHTR;Johnson;Nucl. Eng. Design,2012

4. Leakage flows in high-temperature gas-cooled reactor graphite fuel element;Kaburaki;J. Nucl. Sci. Technol.,1985

5. Design of New Facility for Bypass Flow Experiment;Kanjanakijkasem,2011

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