Investigation on dynamic boiling in sodium cooled fast reactors-Reference-Cited by-同舟云学术

Investigation on dynamic boiling in sodium cooled fast reactors

Published:1970-10 Issue:1 Volume:14 Page:23-42
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Peppler W.,Schlechtendahl E.G.,Schultheiss G.F.

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

Reference40 articles.

1. TRANSFUGUE-I, a digital code for transient two-phase-flow and heat transfer;Noyes;NAA-SR-11008,1965

2. The development and growth of in-core voids due to boiling during fast reactor transients;Noyes,1965

3. Die Ejektion von Natrium aus Reaktorkühlkanälen;Schlechtendahl;Nukleonik,1967

4. Sieden des Kühlmittels in natriumgekühlten schnellen Reaktoren;Schlechtendahl;KFK 1020, EUR 4302 d,1969

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