Search Results - "Lee, Kwi Lim"
-
1
Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel bundle for SFR
Published in Nuclear engineering and technology (01-08-2015)“…Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of a Japanese loop-type sodium-cooled fast reactor, Monju, were investigated…”
Get full text
Journal Article -
2
RANS based CFD methodology for a real scale 217-pin wire-wrapped fuel assembly of KAERI PGSFR
Published in Nuclear engineering and design (01-03-2017)“…•This paper presents a suitable way for a practical RANS based CFD methodology which is applicable to real scale 217-pin wire-wrapped fuel assembly of KAERI…”
Get full text
Journal Article -
3
CFD investigation of three-dimensional flow phenomena in a JAEA 127-pin wire-wrapped fuel assembly
Published in Nuclear engineering and design (01-11-2017)“…•This paper presents RANS based CFD investigation of three-dimensional flow phenomena in JAEA 127-pin wire-wrapped fuel assembly.•The CFD result shows a good…”
Get full text
Journal Article -
4
Thermal-hydraulic effect of wire spacer in a wire-wrapped fuel bundles for SFR
Published in Nuclear engineering and design (15-08-2017)“…•This paper presents that the wire effect on three-dimensional flow field and heat transfer characteristics in a helically wrapped 7-pin fuel assembly mock-up…”
Get full text
Journal Article -
5
THREE-DIMENSIONAL FLOW PHENOMENA IN A WIRE-WRAPPED 37-PIN FUEL BUNDLE FOR SFR
Published in Nuclear engineering and technology (2015)“…Three-dimensional flow phenomena in a wire-wrapped 37-pin fuel assembly mock-up of a Japanese loop-type sodium-cooled fast reactor, Monju, were investigated…”
Get full text
Journal Article -
6
Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor
Published in 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…”
Get full text
Journal Article -
7
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Published in 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…”
Get full text
Journal Article -
8
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Published in 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)…”
Get full text
Journal Article -
9
Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea
Published in Nuclear engineering and technology (01-10-2016)“…The Prototype Gen IV sodium cooled fast reactor (PGSFR) has been developed for the last 4 years, fulfilling the technology demonstration of the burning…”
Get full text
Journal Article -
10
Design evaluation of large-scale sodium integral effect test facility (STELLA-2) using MARS-LMR
Published in Annals of nuclear energy (01-10-2018)“…•The result of STELLA-2 design evaluation showed a good agreement in general trend of representative DBE.•The capability of the DHRS is proved to be effective…”
Get full text
Journal Article -
11
The sensitivity analysis for IHTS and SG due to the Large-scale Sodium-Water Reaction event in PGSFR
Published in Annals of nuclear energy (01-08-2018)“…•Sodium-Water Reaction (SWR) event is analyzed to a sodium-cooled fast reactor.•Behavior and effects of the pressure waves were analyzed by SWAAM-II…”
Get full text
Journal Article -
12
Evaluation of a Sodium–Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor
Published in Nuclear engineering and technology (01-08-2016)“…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…”
Get full text
Journal Article -
13
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Published in Nuclear engineering and technology (01-10-2016)“…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)…”
Get full text
Journal Article -
14
Experimental investigations of the post-CHF heat transfer of R-134a flow boiling in an annulus with spacer grids
Published in Nuclear engineering and design (01-10-2010)“…An experimental study was performed using R-134a in an annulus channel to investigate the heat transfer characteristics in the post-CHF region. The experiments…”
Get full text
Journal Article -
15
The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids
Published in International journal of heat and mass transfer (2008)“…In the present paper, critical heat flux (CHF) experiments of forced convection boiling were performed to investigate the CHF characteristics of a vertical…”
Get full text
Journal Article