Results 1 to 10 of about 3,167 (119)
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 +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.
Chihyung Kim +2 more
doaj +4 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 +4 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
doaj +5 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 +3 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
doaj +1 more source
Advancing the Mechanical Performance of Glasses: Perspectives and Challenges
Advanced Materials, Volume 34, Issue 14, April 7, 2022., 2022 The mechanical performance of glassy materials presents a major challenge in modern glass science and technology. With a focus on visually transparent, inorganic and hybrid glasses, a perspective on the most recent developments in the field is provided herein, emphasizing the importance of translating fundamental insight from glass physics into future ...
Lothar Wondraczek +5 more
wiley +1 more source
Nuclear Technology, 2019 AbstractThe SAS4A safety analysis code, originally developed for the analysis of postulated severe accidents in oxide fuel sodium-cooled fast reactors (SFRs), has been significantly extended to all...
A. M. Tentner, A. Karahan, S. H. Kang
openaire +2 more sources
Preliminary Selection of Device Materials to Locally Transform Thermal into SFR Neutron Spectrum
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 The safe introduction of Generation IV (Gen IV) reactor concepts into operation will require extensive testing of their components. This must be performed under neutronic conditions representative of those expected to prevail inside the new reactor cores when in operation.
N. Chrysanthopoulou +6 more
wiley +1 more source
Fabrication of U‐10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR‐60 Fast Reactor
Science and Technology of Nuclear Installations, Volume 2016, Issue 1, 2016., 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 loading of the metallic fuel, U‐10 wt.%Zr fuel rodlets were fabricated and evaluated for a ...
Ki-Hwan Kim +6 more
wiley +1 more source