Results 21 to 30 of about 171 (84)
Heat transfer characteristics of redan structure in large-scale test facility STELLA-2
Nuclear Engineering and Technology, 2021 The construction of STELLA-2 facility is on-going to demonstrate the safety system of PGSFR and to provide comprehensive understanding of transient behavior under DBEs.
Jung Yoon +4 more
doaj +1 more source
The Contribution of Small Modular Reactors to the Resilience of Power Supply [PDF]
, 2022 In recent years, there has been a growing interest in the design, development and commercialization of nuclear power Small Modular Reactors (SMRs). Actual SMR designs cover the full spectrum of nuclear reactor technologies, including water-, gas-, liquid-
Enrico Zio +2 more
core +1 more source
Large eddy simulation of thermal striping in the upper plenum of the PGSFR [PDF]
Journal of Nuclear Science and Technology, 2014 A computational study of thermal striping in the upper plenum of the prototype generation-IV sodium-cooled fast reactor (PGSFR) being developed at Korea Atomic Energy Research Institute is presented. First, previous experimental and numerical studies on the thermal striping are briefly discussed.
Seok-Ki Choi +3 more
openaire +1 more source
Nuclear Engineering and Technology, 2023 The STELLA-2 is a large-scale sodium thermal-hydraulic integral effect test facility and supports the development of PGSFR. The facility adopted Pump Simulation Loop System (PSLS) concept for the mechanical sodium pump in the reference reactor to control
Jung Yoon +4 more
doaj +1 more source
Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock‐Up at KAERI
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 This paper presents a remote testbed for metallic fuel fabrication using surrogates or depleted uranium. The testbed named “remote fuel fabrication mock‐up (RFFM)” was created at the Korea Atomic Energy Research Institute and specifically designed to incorporate remote operation and maintenance.
Kiho Kim +4 more
wiley +1 more source
Design of large-scale sodium thermal-hydraulic integral effect test facility, STELLA-2
Nuclear Engineering and Technology, 2022 The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS.
Jewhan Lee +4 more
doaj +1 more source
A review: ferritic-martensitic steels – treatment, structure and mechanical properties [PDF]
, 2022 The constantly growing consumption of electricity requires the development and implementation of more powerful and energy-intensive systems of the new generation.
Rostova, H.Yu., Tolstolutska, G.D.
core +1 more source
Nuclear Engineering and Technology, 2020 As the refueling of a sodium-cooled fast reactor is conducted by rotating part of the reactor head without opening it, the monitoring of existing obstacles that can disturb the rotation of the reactor head is one of the most important issues.
Hoe-Woong Kim +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2023 The temperature distribution of the reactor pool under natural circulation induced by the RVACS operation was experimentally studied. According to the Bo’ based similarity law, which could reproduce the temperature distribution of the working fluid under
Min Ho Lee +2 more
doaj +1 more source
Numerical analysis of the electromagnetic force for design optimization of a rectangular direct current electromagnetic pump [PDF]
, 2018 The force of a direct current (DC) electromagnetic pump used to transport liquid lithium was analyzed to optimize its geometrical and electrical parameters by numerical simulation.
Kim, Hee Reyoung, Lee, Geun Hyeong
core +1 more source