Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part I: Scientific facility design-Reference-Cited by-同舟云学术

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Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part I: Scientific facility design

Published:2013-12 Issue: Volume:265 Page:497-513
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Hong Soon-Joon,Lee Doo-Yong,Eoh Jae-Hyuk,Lee Tae-Ho,Lee Yong-Bum

Funder

Ministry of Education, Science and Technology of Korea

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

Reference16 articles.

1. Convection Heat Transfer;Bejan,2004

2. Nuclear Heat Transport;El-Wakil,1971

3. Test Requirements for the Integral Effect Test to Simulate a Sodium-cooled Fast Reactor;Eoh,2011

4. Generation of the MARS-LMR Base Input Data for DFR-600;Ha,2010

5. KALIMER-600 Conceptual Design Report;Hahn,2007

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Scientific design of a large-scale sodium thermal–hydraulic test facility for KALIMER—Part II: Validation of reactor pool design using CFD analyses;Annals of Nuclear Energy;2015-02

2. Construction of a High Temperature Grade 91 Sodium Component Test Loop;Materials Science Forum;2010-06

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