Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor
Authors:
- Young-Kyu LeeYLYoung-Kyu Lee
- Jae-Han LeeJLJae-Han Lee
- Hoe-Woong KimHKHoe-Woong Kim
- Sung-Kyun KimSKSung-Kyun Kim
- Jong-Bum KimJKJong-Bum Kim
Open Access
- 1 June 2017
- journal article
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 49 (4) , 855-864
Abstract
No abstract availableKeywords
Funding Information
- National Research Foundation
- Ministry of Science, ICT and Future Planning (2012M2A8A2025633)
This publication has 5 references indexed in Scilit:
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- Mathematical modelling of performance of safety rod and its drive mechanism in sodium cooled fast reactor during scram actionNuclear Engineering and Design, 2014
- Design, Development, Testing and Qualification of Diverse Safety Rod and Its Drive Mechanism for a Prototype Fast Breeder ReactorJournal of Engineering for Gas Turbines and Power, 2010
- Testing and qualification of Control & Safety Rod and its drive mechanism of Fast Breeder ReactorNuclear Engineering and Design, 2010