Crossflow characteristics of HTGR fuel blocks-Reference-Cited by-同舟云学术

Crossflow characteristics of HTGR fuel blocks

Published:1990-06 Issue:2-3 Volume:120 Page:425-434
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kaburaki Hideo,Takizuka Takakazu

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

Reference6 articles.

1. Public Service Company of Colorado 330-MW(e) High Temperature Gas-Cooled Reactor Research and Development Program;Gulf General Atomic;GA-8038,1967

2. Störung der Kühlmittelverteilung in Blockfömigen durch Bypass-Strömungen;Groehn;Jül-1185,1975

3. Fluid Mechanics Measurements,1983

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

5. A linearized turbulent lubrication theory;Ng;Trans. ASME, J. Basic Engrg.,1965

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