Results 1 to 10 of about 80 (53)
Applicability of the induction bending process to the P91 pipe of the PGSFR
Nuclear Engineering and Technology, 2021 The application of induction bending processes to industrial pipe production is increasing. The induction bending process has the effect of reducing the number of inspections and preventing leaks by reducing the weld of the pipe.
Jong-Bum Kim, Sung Kyun Kim
exaly +4 more sources
Nuclear Engineering and Technology, 2022 KAERI (Korea Atomic Energy Research Institute) developed the conceptual design of PGSFR (Prototype Gen-IV Sodium Cooled Fast Reactor) and Burner Reactor. Since the reactor characteristics of the PGSFR and Burner Reactor are different, the shape, size and
Kang-Soo Kim +2 more
exaly +4 more sources
Nuclear Engineering and Technology, 2016 The Korean Prototype Gen-IV sodium-cooled fast reactor (PGSFR) is supposed to be loaded with a relatively-costly low-enriched U fuel, while its envisaged transuranic fuels are not available for transmutation.
Donny Hartanto, Yonghee Kim
exaly +4 more sources
Nuclear Engineering and TechnologyThe application of the induction bending process in pipe fabrication is expanding across industries, significantly reducing leakage by minimizing welded sections in curved pipes.
Tae-Won Na +5 more
exaly +4 more sources
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology, 2016 Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR).
Kwi Lim Lee +9 more
doaj +8 more sources
Nuclear Engineering and Technology, 2022 Thermal striping is a complex thermal–hydraulic phenomenon caused by fluid temperature fluctuations that can also cause high-cycle thermal fatigue to the structural wall of sodium-cooled fast reactors (SFRs).
Yohan Jung, Sun Rock Choi, Jonggan Hong
doaj +2 more sources
Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor
Science and Technology of Nuclear Installations, 2016 The fabrication technology for metallic fuel has been developed to produce the driver fuel in a PGSFR in Korea since 2007. In order to evaluate the irradiation integrity and validate the in-reactor of the starting metallic fuel with FMS cladding for the ...
Ki-Hwan Kim +5 more
doaj +2 more sources
Nuclear Engineering and Technology, 2016 The design of Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) has been developed and the validation and verification (V&V) activities to demonstrate the system performance and safety are in progress.
Jong-Bum Kim +5 more
doaj +3 more sources
Nuclear Engineering and Technology, 2021 The temperature distribution of an electromagnetic pump was analyzed with a flow rate of 1380 L/min and a pressure of 4 bar designed for the sodium thermo-hydraulic test in the Sodium Test Loop for Safety Simulation and Assessment-Phase 1 (STELLA-1). The
Jaesik Kwak, Hee Reyoung Kim
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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology, 2016 Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to be built by 2028. U–Zr fuel is a driver for the initial core of the PGSFR, and U–transuranics (TRU)–Zr fuel will gradually replace U–Zr fuel through its ...
Chan Bock Lee +4 more
doaj +2 more sources