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Methods and performance of a three-dimensional whole-core transport code DeCART
TLDR
DeCART is a three-dimensional whole-core transport code capable of performing direct core calculations at power generating conditions without involving a priori homogenized few-group constant generation. Expand
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Development of a physics analysis procedure for the prismatic very high temperature gas-cooled reactors
Abstract A new physics analysis procedure has been developed for a prismatic very high temperature gas-cooled reactor based on a conventional two-step procedure for the PWR physics analysis. TheExpand
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DYNAMIC IMPLEMENTATION OF THE EQUIVALENCE THEORY IN THE HETEROGENEOUS WHOLE CORE TRANSPORT CALCULATION
The coarse mesh finite difference (CMFD) formulation is applied to the heterogeneous whole transport calculation as a means of efficient acceleration as well as simplified representation. A pin cellExpand
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Design Verification Program of SMART
Since July of 1997, KAERI (Korea Atomic Energy Research Institute) has been developing an advanced reactor called SMART(System integrated Modular Advanced ReacTor). SMART is a 330MWt integral typeExpand
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Cell Based CMFD Formulation for Acceleration of Whole-core Method of Characteristics Calculations
This Paper is to apply the well-established coarse mesh finite difference(CMFD) method to the method of characteristics(MOC) transport calculation as an acceleration scheme. The CMFD problem is firstExpand
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Monte Carlo Resonance Treatment for the Deterministic Transport Lattice Codes
Transport lattice codes require the resonance integral tables for the resonant nuclides where the resonance integral is a function of the background cross section and can be prepared through aExpand
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Safety Analysis of SMART
SMART is a 330 MWt integral type reactor, which enhances safety by adopting inherent and passive safety design features. The safety analyses have been performed for the major design basis accidentsExpand
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Trip setpoint analysis for the reactor protection system of an advanced integral reactor
Abstract The trip setpoints for the reactor protection system of a 65-MWt advanced integral reactor have been analyzed through sensitivity evaluations by using the Transients and SetpointExpand
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Performance evaluation of an advanced integral reactor against an anticipated transient without scram
Abstract Performance evaluation of KAERI’s advanced integral reactor against an anticipated transient without scram has been carried out with the transients and setpoint simulation/small and mediumExpand
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An Application of a Variable Overpower Trip Function with Multiple Ceilings into an Advanced Integral Reactor
A series of evaluations for an inadvertent control rod withdrawal event has been performed to identify the appropriateness of the reactor protection system of a 65 MWt advanced integral reactor byExpand