Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

Author:

Lee Young-Kyu,Lee Jae-Han,Kim Hoe-Woong,Kim Sung-Kyun,Kim Jong-BumORCID

Funder

National Research Foundation

Ministry of Science, ICT and Future Planning

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference25 articles.

1. Sodium fast reactor, 3rd GIF Symposium 2015/ICONE23 Conference, Japan;Dufour,2015

2. Safety design criteria (SDC) development for generation-IV sodium-cooled fast reactor system, 3rd GIF Symposium 2015/ICONE23 Conference, Japan;Nakai,2015

3. Overview of SFR safety in India, Second Joint GIF-IAEA/INPRO Consultancy Meeting on Safety Aspects of SFRs;Chellapandi,2011

4. Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics;Kamide,2013

5. Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea;Yoo;Nucl. Eng. Technol.,2016

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