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A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
이귀림,하귀석,정재호,최치웅,Taekyeong Jeong,Sang June Ahn,이승원,WON-PYO CHANG,강석훈,유재운 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.5
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). To assess the effectiveness of the inherent safety features of the PGSFR, the system transients during design basis accidents and design extended conditions are analyzed with MARS-LMR and the subchannel blockage events are analyzed with MATRA-LMR-FB. In addition, the invessel source term is calculated based on the super-safe, small, and simple reactor methodology. The results show that the PGSFR meets safety acceptance criteria with a sufficient margin during the events and keeps accidents from deteriorating into more severe accidents.
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THREE-DIMENSIONAL FLOW PHENOMENA IN A WIRE-WRAPPED 37-PIN FUEL BUNDLE FOR SFR
정재호,유진,이귀림,하귀석 한국원자력학회 2015 Nuclear Engineering and Technology Vol.47 No.5
Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of aJapanese loop-type sodium-cooled fast reactor, Monju, were investigated with a numericalanalysis using a general-purpose commercial computational fluid dynamics code, CFX. Complicated and vortical flow phenomena in the wire-wrapped 37-pin fuel assembly werecaptured by a Reynolds-averaged NaviereStokes flow simulation using a shear stresstransport turbulence model. The main purpose of the current study is to understand thethree-dimensional complex flow phenomena in a wire-wrapped fuel assembly to supportthe license issue for the core design. Computational fluid dynamics results show goodagreement with friction factor correlation models. The secondary flow in the corner andedge subchannels is much stronger than that in an interior subchannel. The axial velocityaveraged in the corner and edge subchannels is higher than that averaged in the interiorsubchannels. Three-dimensional multiscale vortex structures start to be formed by aninteraction between secondary flows around each wire-wrapped pin. Behavior of the largescalevortex structures in the corner and edge subchannels is closely related to the relativeposition between the hexagonal duct wall and the helically wrapped wire spacer. Thesmall-scale vortex is axially developed in the interior subchannels. Furthermore, a drivingforce on each wire spacer surface is closely related to the relative position between thehexagonal duct wall and the wire spacer.
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유재운,Jinwook Chang,Jae-Yong Lim,Jin-SikCheon,이태호,김성균,이귀림,Hyung-KookJoo 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.5
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. The PGSFR design has been focused on the robustness of safety systems by enhancing inherent safety characteristics of metal fuel and strengthening passive safety features using natural circulation and thermal expansion. The preliminary safety information document as a major outcome of the first design phase of PGSFR development was issued at the end of 2015. The project entered the second design phase at the beginning of 2016. This paper summarizes the overall structures, systems, and components of nuclear steam supply system and safety characteristics of the PGSFR. The research and development activities to demonstrate the safety performance are also briefly introduced in the paper.
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