SNUEI

Nuclear reactor physics and engineering

연구주제 · Aerospace Engineering

참여 교수

교수학과논문
심형진원자핵공학과27
최성열원자핵공학과9

연결되는 NTIS 분류

에너지/자원만에너지·환경·원자력 확장

핵연료주기/방사성 폐기물 관리기술 8 원자로 노심 기술 7 원자로 계통/핵심기기 기술 1

논문 (피인용 순)

연도논문SNUEI 저자피인용
2015Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation 원자로 계통/핵심기기 기술 › 핵심기기 설계기술
Progress in Nuclear Energy
최성열44
2017Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark
Nuclear Engineering and Technology
심형진35
2014Preliminary conceptual design and cost estimation for Korea Advanced Pyroprocessing Facility Plus (KAPF+) 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Nuclear Engineering and Design
최성열30
2015Performance modeling and analysis of spent nuclear fuel recycling 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
International Journal of Energy Research
최성열23
2016Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method
Annals of Nuclear Energy
심형진21
2014Dynamic analysis of once-through and closed fuel cycle economics using Monte Carlo simulation 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Nuclear Engineering and Design
최성열21
2017Development of Generalized Perturbation Theory Algorithms for Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진20
2016Economic potential of fuel recycling options: A lifecycle cost analysis of future nuclear system transition in China 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Energy Policy
최성열20
2014Dynamic assessments on high-level waste and low- and intermediate-level waste generation from open and closed nuclear fuel cycles in Republic of Korea 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Journal of Nuclear Science and Technology
최성열19
2015Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark
Annals of Nuclear Energy
심형진17
2016Environmental life cycle risk modeling of nuclear waste recycling systems 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Energy
최성열16
2018Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD
Nuclear Engineering and Technology
심형진15
2015Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis
Science and Technology of Nuclear Installations
심형진15
2014Real Variance Estimation by Grouping Histories in Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진13
2015Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis
Science and Technology of Nuclear Installations
심형진12
2023Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD 원자로 노심 기술 › 노심 핵설계 기술
Nuclear Engineering and Technology
심형진12
2014Preliminary conceptual design and cost estimation for SFR Fuel Manufacturing Facility (SFMF) 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Nuclear Engineering and Design
최성열10
2014Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weighted Correlated Sampling Method 원자로 노심 기술 › 노심 핵설계 기술
Nuclear Science and Engineering
심형진9
2023Development of deep convolutional neural network for prediction of cycle maximum pin power peaking factor in pressurized water reactor 원자로 노심 기술 › 노심 핵설계 기술
Annals of Nuclear Energy
심형진8
2025Verification of the nTRACER/CTF code system for full core high resolution cycle analysis with the OECD/NEA TVA Watts Bar Unit 1 benchmark 원자로 노심 기술 › 노심 핵설계 기술
Annals of Nuclear Energy
심형진7
2014McCARD for neutronics design and analysis of research reactor cores
Annals of Nuclear Energy
심형진7
2024Development of a GPU-enhanced time-dependent Monte Carlo neutron transport version of McCARD
EPJ Nuclear Sciences & Technologies
심형진6
2014UNCERTAINTY PROPAGATION ANALYSIS FOR YONGGWANG NUCLEAR UNIT 4 BY MCCARD/MASTER CORE ANALYSIS SYSTEM 원자로 노심 기술 › 노심 핵설계 기술
Nuclear Engineering and Technology
심형진6
2017Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance Data
Nuclear Science and Engineering
심형진6
2023Comparison of BANDI-60 core designs using Pyrex burnable absorber and annular fuel embedding gadolinia wire 원자로 노심 기술 › 노심 핵설계 기술
Annals of Nuclear Energy
심형진5
2015Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly
Nuclear Technology
심형진5
2019Estimation of kinetics parameters by Monte Carlo fixed-source calculations for point kinetic analysis of accelerator-driven system
Journal of Nuclear Science and Technology
심형진5
2017Multinational planning of nuclear energy systems in Asia 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Energy Sources Part B Economics Planning and Policy
최성열4
2018Sensitivity and uncertainty analysis of nuclear reactor reactivity coefficients by Monte Carlo second-order perturbation method
Annals of Nuclear Energy
심형진3
2018Determination of an Effective Detector Position for Pulsed-Neutron-Source Alpha Measurement by Time-Dependent Monte Carlo Neutron Transport Simulations
Science and Technology of Nuclear Installations
심형진3
2024Evaluation of tritium production capability of the 5 MWe gas-cooled graphite-moderated reactor at Yongbyon using tritium-producing burnable absorber rods
Nuclear Engineering and Technology
심형진2
2024Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진1
2022Monte Carlo Sensitivity Analyses of Isothermal Temperature Coefficient in Solid-Moderated and Solid-Reflected Cores at Kyoto University Critical Assembly 원자로 노심 기술 › 노심 핵설계 기술
Annals of Nuclear Energy
심형진1
2023Sensitivity of a control rod worth estimate to neutron detector position by time-dependent Monte Carlo simulations of the rod drop experiment
Nuclear Engineering and Technology
심형진1
2024Design of open-tank-in-pool-type educational critical assemblies using UO2 and U-7Mo fuels
Annals of Nuclear Energy
심형진0
2026Energy spectrum assessment of ion beam induced neutrons estimated by Monte Carlo codes for nuclear data production system at RAON
Nuclear Engineering and Technology
심형진0

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최성열 · 심형진

논문 36

Performance modeling and analysis of spent nuclear fuel recycling · Environmental life cycle risk modeling of nuclear waste recycling syst · Dynamic analysis of once-through and closed fuel cycle economics using · Economic potential of fuel recycling options: A lifecycle cost analysi · Multinational planning of nuclear energy systems in Asia · Advanced passive design of small modular reactor cooled by heavy liqui · Dynamic assessments on high-level waste and low- and intermediate-leve · Preliminary conceptual design and cost estimation for Korea Advanced P · Sensitivity and uncertainty analysis of nuclear reactor reactivity coe · Preliminary conceptual design and cost estimation for SFR Fuel Manufac · Memory-efficient calculations of adjoint-weighted tallies by the Monte · Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weig · Dynamic Monte Carlo transient analysis for the Organization for Econom · Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity · Estimation of kinetics parameters by Monte Carlo fixed-source calculat · Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energ · McCARD for neutronics design and analysis of research reactor cores · Monte Carlo burnup and its uncertainty propagation analyses for VERA d · Real Variance Estimation by Grouping Histories in Monte Carlo Eigenval · UNCERTAINTY PROPAGATION ANALYSIS FOR YONGGWANG NUCLEAR UNIT 4 BY MCCAR · Development of Generalized Perturbation Theory Algorithms for Monte Ca · Determination of an Effective Detector Position for Pulsed-Neutron-Sou · Evaluation of tritium production capability of the 5 MWe gas-cooled gr · Development of deep convolutional neural network for prediction of cyc · Comparison of BANDI-60 core designs using Pyrex burnable absorber and · Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis · Verification of the nTRACER/CTF code system for full core high resolut · Sensitivity of a control rod worth estimate to neutron detector positi · Energy spectrum assessment of ion beam induced neutrons estimated by M · Design of open-tank-in-pool-type educational critical assemblies using · Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Ki · Development of a GPU-enhanced time-dependent Monte Carlo neutron trans · Advances for the time-dependent Monte Carlo neutron transport analysis · Real variance analysis of Monte Carlo eigenvalue calculation by McCARD · Monte Carlo Sensitivity Analyses of Isothermal Temperature Coefficient · Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysi

학문분야 1

Aerospace Engineering