Results 11 to 20 of about 171 (84)
Fabrication of U-10 wt.%Zr Metallic Fuel Rodlets for Irradiation Test in BOR-60 Fast Reactor [PDF]
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 +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.
Nak Hyun KIM
exaly +4 more sources
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea [PDF]
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 +3 more sources
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor [PDF]
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
Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor [PDF]
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 +3 more sources
Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor [PDF]
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 +3 more sources
An Optimal Design Approach for the Decay Heat Removal System in PGSFR
Volume 1C, Symposia: Fundamental Issues and Perspectives in Fluid Mechanics; Industrial and Environmental Applications of Fluid Mechanics; Issues and Perspectives in Automotive Flows; Gas-Solid Flows: Dedicated to the Memory of Professor Clayton T. Crowe; Numerical Methods for Multiphase Flow; Transport Phenomena in Energy Conversion From Clean and Sustainable Resources; Transport Phenomena in Materials Processing and Manufacturing Processes, 2014 Sodium-cooled Fast Reactor (SFR) is one of the generation IV (Gen-IV) nuclear reactors. Prototype Gen-IV SFR (PGSFR) is a SFR being developed in Korea Atomic Energy Research Institute (KAERI).
Dehee Kim, Jaehyuk Eoh, Tae-Ho Lee
core +3 more sources
Computation of Thermal Striping in the Upper Plenum of PGSFR
Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, 2014 A computational study of a thermal striping in the upper plenum of the PGSFR (Prototype Generation-IV Sodium-cooled Fast Reactor) being developed at KAERI (Korea Atomic Energy Research Institute) is presented. First, previous experimental and numerical studies on the thermal striping are briefly discussed.
Dong-Eun Kim +3 more
core +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
Development of In-Service Inspection Techniques for PGSFR [PDF]
Transactions of the Korean Society of Pressure Vessels and Piping, 2016 Gyeong Hoi Koo +6 more
core +3 more sources