Results 1 to 10 of about 171 (84)
Numerical analysis of the temperature distribution of the EM pump for the sodium thermo-hydraulic test loop of the GenIV PGSFR [PDF]
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
exaly +6 more sources
Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector [PDF]
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 +6 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 +5 more sources
Optimization of outer core to reduce end effect of annular linear induction electromagnetic pump in prototype Generation-IV sodium-cooled fast reactor [PDF]
Nuclear Engineering and Technology, 2020 An annular linear induction electromagnetic pump (ALIP) which has a developed pressure of 0.76 bar and a flow rate of 100 L/min is designed to analysis end effect which is main problem to use ALIP in thermohydraulic system of the prototype generation-IV ...
Jaesik Kwak, Hee Reyoung Kim
doaj +8 more sources
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.
Nak Hyun Kim +2 more
exaly +4 more sources
On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes [PDF]
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 +5 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
exaly +4 more sources
Design and evaluation of reactor vault cooling system in PGSFR
Nuclear Engineering and Design, 2020 Abstract 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
exaly +3 more sources
Improvement of aseismic performance of a PGSFR PHTS pump
Nuclear Engineering and Technology, 2020 Abstract A design study was performed to improve the limit aseismic performance (LSP) of a primary heat transport system (PHTS) pump. This pump is part of the primary equipment of a prototype generation IV sodium-cooled fast reactor (PGSFR). The LSP is the maximum allowable seismic load that still ensures structural integrity. To calculate the LSP of
Jae Han Lee +4 more
exaly +4 more sources
Nuclear Engineering and Technology, 2023 The application of the induction bending process to pipe systems in various industrial fields is increasing. Recently, efforts have also been made to apply this bending process to nuclear power plants because it can innovatively reduce welded parts of ...
Nak Hyun KIM
exaly +3 more sources