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MAINTAINING THE CLOSE-TO-CRITICAL STATE OF THORIUM FUEL CORE OF HYBRID REACTOR OPERATED UNDER CONTROL BY D-T FUSION NEUTRON FLUX
Nuclear Engineering and Technology
2021 .06
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 Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
Time-frequency analysis of reactor neutron noise under bubble disturbance and control rod vibration
Nuclear Engineering and Technology
2021 .04
A feasibility study of the Iranian Sun mather type plasma focus source for neutron capture therapy using MCNP X2.6, Geant4 and FLUKA codes
Nuclear Engineering and Technology
2020 .01
Characterization of a Neutron Beam Following Reconfi guration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements
Nuclear Engineering and Technology
2016 .01
A high-stability neutron generator for industrial online elemental analysis
Nuclear Engineering and Technology
2024 .04
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
Study on Stiffened-Plate Structure Response in Marine Nuclear Reactor Operation Environment
한국해양공학회지
2023 .10
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
Applicability of the Kr ? ko nuclear power plant core Monte Carlo model for the determination of the neutron source term
Nuclear Engineering and Technology
2021 .11
Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor
Nuclear Engineering and Technology
2018 .01
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
연구용 원자로의 건전성 평가를 위한 수치해석적 중성자 조사 재료변형 예측기법 개발
한국압력기기공학회 논문집
2024 .06
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
Conceptual design of a high neutron fl ux research reactor core with low enriched uranium fuel and low plutonium production
Nuclear Engineering and Technology
2020 .01
Nano Yttrium-90 and Rhenium-188 production through medium medical cyclotron and research reactor for therapeutic usages: A Simulation study
Nuclear Engineering and Technology
2023 .05
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