Results 11 to 20 of about 128 (71)
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
Nuclear Engineering and Technology, 2016 The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning capability of transuranic elements included in light water reactor spent nuclear fuel.
Jaewoon Yoo +7 more
doaj +2 more sources
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 +2 more sources
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 +2 more sources
Nuclear Engineering and Technology, 2016 The prototype generation IV sodium-cooled fast reactor (PGSFR) has been developed by the Korea Atomic Energy Research Institute. This reactor uses sodium as a reactor coolant to transfer the core heat energy to the turbine.
Sang June Ahn +9 more
doaj +2 more sources
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 +2 more sources
Nuclear Engineering and TechnologyThis study evaluated the high-temperature creep structural integrity of P91 induction-bent piping for Prototype Gen-IV Sodium-cooled Fast Reactors (PGSFR) through specimen creep tests and bent pipe structural creep test alongside inelastic analysis ...
Tae-Won Na +5 more
doaj +2 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 +2 more sources
Heat rejection effect study on large-scale sodium test facility STELLA-2
Nuclear Engineering and TechnologyThe STELLA-2 facility is a large-scale sodium test facility to support the development of PGSFR and is accumulating extensive experiment data. The experiment campaigns of STELLA-2 are mostly planned to be transient and therefore it is very challenging to
Jewhan Lee +3 more
doaj +2 more sources
Nuclear Engineering and TechnologyThis paper presents a validation study of the subchannel analysis code SLTHEN used for the core thermal-hydraulic design of the Prototype Gen-IV sodium-cooled fast reactor (PGSFR).
Sun Rock Choi +4 more
doaj +2 more sources