Mathematical modelling of performance of safety rod and its drive mechanism in sodium cooled fast reactor during scram action-Reference-Cited by-同舟云学术

Mathematical modelling of performance of safety rod and its drive mechanism in sodium cooled fast reactor during scram action

Published:2014-10 Issue: Volume:278 Page:601-617
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Rajan Babu V.,Thanigaiyarasu G.,Chellapandi P.

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.

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3. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles – bundle friction factors, sub-channel friction factors and mixing parameters;Cheng;Nucl. Eng. Des.,1986

4. Design of the prototype fast breeder reactor;Chetal;Nucl. Eng. Des.,2006

5. A mathematical model of a control rod drop;Donis;Nucl. Eng. Des.,1972

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