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Calculation of kinetic parameters ? eff and ? with modifi ed open source Monte Carlo code OpenMC(TD)
Nuclear Engineering and Technology
2022 .03
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
Clustering and traveling waves in the Monte Carlo criticality simulation of decoupled and confi ned media
Nuclear Engineering and Technology
2017 .01
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
Time-frequency analysis of reactor neutron noise under bubble disturbance and control rod vibration
Nuclear Engineering and Technology
2021 .04
A high-density gamma white spots-Gaussian mixture noise removal method for neutron images denoising based on Swin Transformer UNet and Monte Carlo calculation
Nuclear Engineering and Technology
2024 .02
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
Nuclear Engineering and Technology
2017 .06
Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
In-line (α,n) source sampling methodology for monte carlo radiation transport simulations
Nuclear Engineering and Technology
2017 .01
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
Dynamic 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
2017 .01
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
Limits on the efficiency of event-based algorithms for Monte Carlo neutron transport
Nuclear Engineering and Technology
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
Diamond-based neutron scatter camera
Nuclear Engineering and Technology
2022 .04
Optimization of Target, Moderator, and Collimator in the Accelerator-based Boron Neutron Capture Therapy System: A Monte Carlo Study
Nuclear Engineering and Technology
2021 .06
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
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