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Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method
Nuclear Engineering and Technology
2024 .06
Study on Stiffened-Plate Structure Response in Marine Nuclear Reactor Operation Environment
한국해양공학회지
2023 .10
Simulation-based Anomaly Detection in Nuclear Reactors
대한산업공학회 추계학술대회 논문집
2020 .11
Inverse method to obtain reactivity in nuclear reactors with P1 point reactor kinetics model using matrix formulation
Nuclear Engineering and Technology
2021 .02
시뮬레이션 데이터 생성을 통한 기계학습 기반 원자로 노심 이상 탐지 방법론
대한산업공학회지
2021 .04
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
Big Data Analysis of Public Acceptance of Nuclear Power in Korea
Nuclear Engineering and Technology
2017 .06
Legal Policy Study on Nuclear Liability Principle of Nuclear Operator Under Korea Nuclear Liability Law
한국방사성폐기물학회 학술대회
2018 .01
Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap
Nuclear Engineering and Technology
2020 .11
An Applicable Study on the Fast Neutron Detection for Nuclear Material Accountancy
한국방사성폐기물학회 학술대회
2019 .01
Development of classification criteria for non-reactor nuclear facilities in Korea
Nuclear Engineering and Technology
2023 .02
Challenges in nuclear energy adoption: Why nuclear energy newcomer countries put nuclear power programs on hold?
Nuclear Engineering and Technology
2024 .04
Neutronics Analysis of a 200 kWe Space Nuclear Reactor with an Integrated Honeycomb Core Design
Nuclear Engineering and Technology
2022 .12
Design of a Mixed-Spectrum Reactor With Improved Proliferation Resistance for Long-Lived Applications
방사성폐기물학회지
2018 .01
Development of easy-to-use interface for nuclear transmutation computing, VCINDER code
Nuclear Engineering and Technology
2018 .01
연구용 원자로의 건전성 평가를 위한 수치해석적 중성자 조사 재료변형 예측기법 개발
한국압력기기공학회 논문집
2024 .06
Multi-Scale and Multi-Physics Approach to Safety Analysis of Nuclear Reactor
한국전산유체공학회 학술대회논문집
2022 .10
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
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