SNUEI

몬테카를로 시뮬레이션 monte carlo simulation

방법 · 계산·시뮬레이션

30연구단 논문
6교수
499억 국가 R&D(2015–24)
+37%증가율
7.87%서울대 비중

난수를 이용한 반복 표본 추출로 확률적 현상이나 불확실성을 수치적으로 계산하는 방법이다.

연도별 연구단 논문

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국가 R&D 과제 동향 (NTIS, 억 원)

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2015–2024 과제 레코드 451건 · 10년 499억 · 2015–19 대비 2020–24 +37% · 대학 수행 84.8% · 서울대(본교) 7.87%. 매칭: 영문 키워드 'monte carlo simulation', 국문 '몬테카를로'. 기관운영비·인력양성·출연연 주요사업비 등 과제 아닌 레코드는 뺐다.

매칭 과제의 NTIS 표준분류(1순위, 연구비 비중): 원자력 > 방사선기술 17% · 원자력 > 원자력 계측/제어기술 9% · 원자력 > 원자력안전기술 7% · 정보/통신 > 정보 이론 5%

최근 주요 과제 (2022–2024, 연차 정부연구비 순)

연도과제수행기관부처억
2024양자 컴퓨팅 몬테 카를로 해석 기반의 방사선 치료 계획 고속화 및 환자 맞춤형 방사선 치료 임상 적용 연구연세대학과학기술정보통신부10.0
2022해체 방사선학적 정보 실시간 측정 및 가상현실 기반 공정 평가 기술개발(재)한국원자력연구원과학기술정보통신부5.3
2022DDA(Differential Die-Away) 기법 기반 특정핵물질 생성량 평가 기술 개발한양대학원자력안전위원회5.2
2022핵연료집합체 부분결손 검증을 위한 방출단층촬영기술 개발연세대학원자력안전위원회4.7
2024DDA(Differential Die-Away) 기법 기반 특정핵물질 생성량 평가기술 개발한양대학원자력안전위원회4.2
2024다공소재 수소 흡착 엔탈피 및 기공크기 조절을 통한 수소저장 성능 극대화 연구한국과학기술연구원과학기술정보통신부3.5
2022저농축우라늄 기반 자연순환 장수명 소형용융염고속로 핵심기술 연구개발한국과학기술원과학기술정보통신부3.0
2022메르스 바이러스 확산 경로 탐지 및 방제기술 개발에 관한 연구: 대중교통 이용자를 중심으로서울시립대학과학기술정보통신부3.0

교수

교수학과논문2022년 이후
심형진원자핵공학과226
강상규조선해양공학과32
나용수원자핵공학과22
서유택조선해양공학과10
최성열원자핵공학과10
박정원화학생물공학부10

연결되는 NTIS 분류

에너지/자원만에너지·환경·원자력 확장

원자로 노심 기술 4 신재생에너지 2 핵연료주기/방사성 폐기물 관리기술 1 핵융합 1

논문 (최신순)

연도논문SNUEI 저자피인용
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
2025Real-time organic scintillator neutron spectrum unfolding using a deep learning approach and data generated from TRIASSIC and MCNP
Nuclear Engineering and Technology
나용수1
2024Development of a GPU-enhanced time-dependent Monte Carlo neutron transport version of McCARD
EPJ Nuclear Sciences & Technologies
심형진6
2024The impact of stray magnetic fields on the KSTAR NBI performance 핵융합
Fusion Engineering and Design
나용수2
2024Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Kinetics Model in Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진1
2023Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD 원자로 노심 기술 › 노심 핵설계 기술
Nuclear Engineering and Technology
심형진12
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
2022Techno-economic analysis and Monte Carlo simulation of green hydrogen production technology through various water electrolysis technologies 신재생에너지 › 수소
Energy Conversion and Management
강상규329
2022Techno-economic analysis and Monte Carlo simulation for green hydrogen production using offshore wind power plant 신재생에너지 › 수소
Energy Conversion and Management
강상규251
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
2019Stochastic techno-economic analysis of power-to-gas technology for synthetic natural gas production based on renewable H2 cost and CO2 tax credit
Journal of Energy Storage
강상규51
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
2018Ferroelectric Polarization-Switching Dynamics and Wake-Up Effect in Si-Doped HfO2
ACS Applied Materials & Interfaces
박정원137
2018Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD
Nuclear Engineering and Technology
심형진15
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
2018Sensitivity and uncertainty analysis of nuclear reactor reactivity coefficients by Monte Carlo second-order perturbation method
Annals of Nuclear Energy
심형진3
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
2017Development of Generalized Perturbation Theory Algorithms for Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진20
2017Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance Data
Nuclear Science and Engineering
심형진6
2016Memory-efficient calculations of adjoint-weighted tallies by the Monte Carlo Wielandt method
Annals of Nuclear Energy
심형진21
2015Real variance analysis of Monte Carlo eigenvalue calculation by McCARD for BEAVRS benchmark
Annals of Nuclear Energy
심형진17
2015Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis
Science and Technology of Nuclear Installations
심형진15
2015Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis
Science and Technology of Nuclear Installations
심형진12
2015Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly
Nuclear Technology
심형진5
2014Risk-based determination of design pressure of LNG fuel storage tanks based on dynamic process simulation combined with Monte Carlo method
Reliability Engineering & System Safety
서유택34
2014Dynamic analysis of once-through and closed fuel cycle economics using Monte Carlo simulation 핵연료주기/방사성 폐기물 관리기술 › 사용후핵…
Nuclear Engineering and Design
최성열21
2014Real Variance Estimation by Grouping Histories in Monte Carlo Eigenvalue Calculations
Nuclear Science and Engineering
심형진13
2014Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weighted Correlated Sampling Method 원자로 노심 기술 › 노심 핵설계 기술
Nuclear Science and Engineering
심형진9
2014McCARD for neutronics design and analysis of research reactor cores
Annals of Nuclear Energy
심형진7
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

인접 그래프

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이 문서와 연결된 페이지

교수 3

나용수 · 강상규 · 심형진

논문 30

Techno-economic analysis and Monte Carlo simulation of green hydrogen · Monte Carlo Fuel Temperature Coefficient Estimation by an Adjoint-Weig · Dynamic analysis of once-through and closed fuel cycle economics using · UNCERTAINTY PROPAGATION ANALYSIS FOR YONGGWANG NUCLEAR UNIT 4 BY MCCAR · Development of Generalized Perturbation Theory Algorithms for Monte Ca · Techno-economic analysis and Monte Carlo simulation for green hydrogen · Risk-based determination of design pressure of LNG fuel storage tanks · Sensitivity and uncertainty analysis of nuclear reactor reactivity coe · Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity · Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energ · Monte Carlo burnup and its uncertainty propagation analyses for VERA d · Advances for the time-dependent Monte Carlo neutron transport analysis · Monte Carlo Sensitivity Analyses of Isothermal Temperature Coefficient · McCARD for neutronics design and analysis of research reactor cores · The impact of stray magnetic fields on the KSTAR NBI performance · Development of a GPU-enhanced time-dependent Monte Carlo neutron trans · Memory-efficient calculations of adjoint-weighted tallies by the Monte · Dynamic Monte Carlo transient analysis for the Organization for Econom · Estimation of kinetics parameters by Monte Carlo fixed-source calculat · Real Variance Estimation by Grouping Histories in Monte Carlo Eigenval · Real-time organic scintillator neutron spectrum unfolding using a deep · Sensitivity of a control rod worth estimate to neutron detector positi · Ferroelectric Polarization-Switching Dynamics and Wake-Up Effect in Si · Real variance analysis of Monte Carlo eigenvalue calculation by McCARD · Stochastic techno-economic analysis of power-to-gas technology for syn · Determination of an Effective Detector Position for Pulsed-Neutron-Sou · Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis · Energy spectrum assessment of ion beam induced neutrons estimated by M · Kinetics Parameters Estimation for the Coupled Neutron-Photon Point Ki · Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysi