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http://dx.doi.org/10.9713/kcer.2019.57.1.28

Investigation on Performance Analysis of Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor  

Park, Sun Hee (SFR System Design Division, Korea Atomic Energy Research Institute)
Han, Ji-Woong (SFR System Design Division, Korea Atomic Energy Research Institute)
Publication Information
Korean Chemical Engineering Research / v.57, no.1, 2019 , pp. 28-41 More about this Journal
Abstract
We carried out performance analysis of Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor. We analyzed transient-dynamic behavior of fluids inside the steam generator to vent into a sodium dump tank or a water dump tank when tubes in the steam generator were broken to cause a large-water-leak accident. Accordingly, we preliminarily evaluated design requirements of our system. Our results showed that sodium in the shell side of the steam generator and in Intermediate Heat Transport System was completely vented within 50 s and feed water in the tube side of the steam generator was completely vented within 2.5 s. It was analyzed that pressure of the tube side of the steam generator was higher than pressure of the shell side of the steam generator, which showed that sodium in the shell side did not flow into the tube side. Our results are expected to be used as basis information to performance analysis of Sodium-Water Reaction Pressure Relief System of Prototype Generation-IV Sodium-Cooled Fast Reactor.
Keywords
Sodium-cooled Fast Reactor; Sodium-Water Reaction; Pressure Relief System; Performance Analysis;
Citations & Related Records
Times Cited By KSCI : 4  (Citation Analysis)
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