Post shut-down decay heat removal from nuclear reactor core by natural convection loops in sodium pool-Reference-Cited by-同舟云学术

Post shut-down decay heat removal from nuclear reactor core by natural convection loops in sodium pool

Published:2016-05 Issue: Volume:301 Page:59-73
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Rajamani A.,Sundararajan T.,Prasad B.V.S.S.S.,Parthasarathy U.,Velusamy K.

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

Reference24 articles.

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2. An advanced thermohydraulic simulation code for transients in LMFBRs (SSC-L Code);Agrawal,1978

3. ANSYS FLUENT Manual, Ver 12.1, ANSYS Inc.

4. Sodium thermal-hydraulics in the pool LMFBR primary vessel;Azarian;Nucl. Eng. Des.,1990

5. Safety conclusions from startup test and from the analysis of core behaviour of PHENIX;Clauzon,1976

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