Results 21 to 30 of about 128 (71)
Nuclear Engineering and TechnologyThe Korea Atomic Energy Research Institute (KAERI) is developing the long-life sodium-cooled fast reactor SALUS-100, designed for continuous 20-year operation without refueling. The concept adapts the proven technology of the Prototype Generation-IV SFR (
Junkyu Han +8 more
doaj +2 more sources
Considerations of Stress Assessment Methodology for BOP Pipings of PGSFR
Transactions of the Korean Society of Pressure Vessels and Piping, 2016 Young Jin Oh +2 more
openaire +3 more sources
SFR Safety Experiments in Support of PGSFR Licensing: Final CRADA Report [PDF]
, 2021 exaly +2 more sources
Heat transfer characteristics of redan structure in large-scale test facility STELLA-2
Nuclear Engineering and Technology, 2021 The construction of STELLA-2 facility is on-going to demonstrate the safety system of PGSFR and to provide comprehensive understanding of transient behavior under DBEs.
Jung Yoon +4 more
doaj +1 more source
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
Seong Hyeon Lee +4 more
openaire +1 more source
Large eddy simulation of thermal striping in the upper plenum of the PGSFR [PDF]
Journal of Nuclear Science and Technology, 2014 A computational study of thermal striping in the upper plenum of the prototype generation-IV sodium-cooled fast reactor (PGSFR) being developed at Korea Atomic Energy Research Institute is presented. First, previous experimental and numerical studies on the thermal striping are briefly discussed.
Seok-Ki Choi +3 more
openaire +1 more source
Metallic Fuel Fabrication Process Development in Remote Fuel Fabrication Mock‐Up at KAERI
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 This paper presents a remote testbed for metallic fuel fabrication using surrogates or depleted uranium. The testbed named “remote fuel fabrication mock‐up (RFFM)” was created at the Korea Atomic Energy Research Institute and specifically designed to incorporate remote operation and maintenance.
Kiho Kim +4 more
wiley +1 more source
Nuclear Engineering and Technology, 2020 As the refueling of a sodium-cooled fast reactor is conducted by rotating part of the reactor head without opening it, the monitoring of existing obstacles that can disturb the rotation of the reactor head is one of the most important issues.
Hoe-Woong Kim +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 ISFRA (Integrated SFR Analysis Program for PSA) computer program has been developed for simulating the response of the PGSFR pool design with metal fuel during a severe accident.
Churl Yoon +4 more
doaj +1 more source
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