A theoretical model with variable masses for the molten fuel-sodium thermal interaction in a nuclear fast reactor-Reference-Cited by-同舟云学术

A theoretical model with variable masses for the molten fuel-sodium thermal interaction in a nuclear fast reactor

Published:1975-11 Issue:2 Volume:34 Page:181-201
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Caldarola L.

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

Reference9 articles.

1. Theoretical studies on the fast reactor maximum accident;Hicks;ANL 7120,1965

2. Current status of knowledge of molten fuel/sodium thermal interaction;Caldarola,1974

3. A theoretical model for the molten fuel-sodium interaction in a nuclear fast reactor;Caldarola;Nucl. Eng. Des.,1972

4. Theoretical models for the molten fuel-sodium interaction;Caldarola,1972

5. The Karlsruhe variable mass model for the description of the fuel/coolant interaction;Caldarola,1973

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