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http://dx.doi.org/10.20466/KPVP.2016.12.1.134

Drop Performance Test of Control Rod Assembly for Prototype Gen-IV Sodium-cooled Fast Reactor  

Lee, Young Kyu (한국원자력연구원)
Kim, Hoe Woong (한국원자력연구원)
Lee, Jae Han (한국원자력연구원)
Koo, Gyeong Hoi (한국원자력연구원)
Kim, Jong Bum (한국원자력연구원)
Kim, Sung Kyun (한국원자력연구원)
Publication Information
Transactions of the Korean Society of Pressure Vessels and Piping / v.12, no.1, 2016 , pp. 134-140 More about this Journal
Abstract
The Control Rod Assembly (CRA) controls the reactor power by adjusting its position in the reactor core during normal operation and should be quickly inserted into the reactor core by free drop under scram condition to shut down chain reactions. Therefore, the drop time of the CRA is one of important factors for the safety of the nuclear reactor and must be experimentally verified. This study presents the drop performance test of the CRA which has been conceptually designed for the Proto-type Generation IV Sodium-cooled Fast Reactor. During the test, the CRA was free dropped from a height of 1 m under different flow rate conditions and its drop time was measured. The results showed that the drop time of the CRA increased as the flow rate increased; the average drop times of the CRA were approximately 1.527 seconds, 1.599 seconds and 1.676 seconds at 0%, 100% and 200% of design flow rates, respectively.
Keywords
Sodium-cooled fast reactor; Liquid metal; Spent nuclear fuel; Control rod assembly; Control rod drive mechanism; Scram; Drop performance test; Residual magnetization; Free drop; Drop time;
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