Investigations on the flow and temperature distribution downstream of local coolant blockages in rod bundle subassemblies-Reference-Cited by-同舟云学术

Investigations on the flow and temperature distribution downstream of local coolant blockages in rod bundle subassemblies

Published:1974 Issue:2 Volume:31 Page:266-279
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kirsch D.

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

Reference22 articles.

1. Cooling disturbances in the core of sodium-cooled fast reactors as causes of fast failure propagation;Gast;Nucl. Eng. Des.,1970

2. Die Ausbreitung örtlicher Störungen im Kern Schneller Natriumgekühlter Reaktoren und ihre Bedeutung für die Reaktorsicherheit;Gast;KFK 1380,1970

3. Loss-of-coolant accidents in a large sodium-cooled fast reactor;Judd;ANL-7120,1965

4. Evaluation of dryout and flow instability in the wake downstream of a blockage in a LMFBR subassembly;Fauske;Trans. Amer. Nucl. Soc.,1972

5. Coolant temperature downstream of a subassembly blockage;Crawford;Trans. Amer. Nucl. Soc.,1972

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