Design and evaluation of reactor vault cooling system in PGSFR
Nuclear Engineering and Design, 2020Abstract In the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR), a Reactor Vault Cooling System (RVCS) is prepared to maintain the structural integrity of the reactor vessel and the concrete during normal operation as well as to mitigate accidents during severe accident conditions.
Sujin Yeom +2 more
exaly +2 more sources
An Optimal Design Approach for the Decay Heat Removal System in PGSFR
Volume 1C, Symposia: Fundamental Issues and Perspectives in Fluid Mechanics; Industrial and Environmental Applications of Fluid Mechanics; Issues and Perspectives in Automotive Flows; Gas-Solid Flows: Dedicated to the Memory of Professor Clayton T. Crowe; Numerical Methods for Multiphase Flow; Transport Phenomena in Energy Conversion From Clean and Sustainable Resources; Transport Phenomena in Materials Processing and Manufacturing Processes, 2014 Sodium-cooled Fast Reactor (SFR) is one of the generation IV (Gen-IV) nuclear reactors. Prototype Gen-IV SFR (PGSFR) is a SFR being developed in Korea Atomic Energy Research Institute (KAERI). Decay Heat Removal System (DHRS) in the PGSFR has a safety function to make shutdown the reactor under abnormal plant conditions.
Dehee Kim, Jaehyuk Eoh, Tae-Ho Lee
core +4 more sources
Design and validation of a fuel assembly simulator for PGSFR reactor flow distribution test facility
Nuclear Engineering and Design, 2020 Abstract A test facility to investigate the flow characteristics inside reactor vessel for the Prototype Gen-IV Sodium-cooled Fast Reactor was constructed. In the test facility, reactor vessel and the main in-vessel components are linearly reduced at a scaling ratio of 1/5 and water is used as the working fluid.
Woo Shik Kim +4 more
openaire +2 more sources
Large eddy simulation of thermal striping in the upper plenum of the PGSFR
Journal of Nuclear Science and Technology, 2015Seok-Ki Choi
exaly
Sensitivity and uncertainty analysis for ULOF of PGSFR using PAPIRUS
Annals of Nuclear Energy, 2017Chiwoong Choi, Kwi-Seok Ha
exaly
Thermal-hydraulic analyses of passive reactor vault cooling system (RVCS) in PGSFR using MARS-LMR
Annals of Nuclear Energy, 2018Chiwoong Choi, Taekyeong Jeong
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Assessment of ex-core neutron detectors in prototype Gen-IV sodium-cooled fast reactor (PGSFR)
Annals of Nuclear Energy, 2019Donny Hartanto, Jae-Yong Lim
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Analyses of UTOP events for the design of control rod stop system in PGSFR using MARS-LMR
Annals of Nuclear Energy, 2016Chiwoong Choi, Hae-Yong Jeong
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Heat transfer performance test of PDHRS heat exchangers of PGSFR using STELLA-1 facility
Nuclear Engineering and Design, 2017Jonggan Hong +2 more
exaly