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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
High accurate three-dimensional neutron noise simulator based on GFEM with unstructured hexahedral elements
Nuclear Engineering and Technology
2019 .01
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
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
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
연구용 원자로의 건전성 평가를 위한 수치해석적 중성자 조사 재료변형 예측기법 개발
한국압력기기공학회 논문집
2024 .06
Adaptive group of ink drop spread: a computer code to unfold neutron noise sources in reactor cores
Nuclear Engineering and Technology
2017 .01
Calibration of digital wide-range neutron power measurement channel for open-pool type research reactor
Nuclear Engineering and Technology
2018 .01
A new approach for calculation of the neutron noise of power reactor based on Telegrapher's theory: Theoretical and comparison study between Telegrapher's and diffusion noise
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
A new surrogate method for the neutron kinetics calculation of nuclear reactor core transients
Nuclear Engineering and Technology
2024 .09
Transient Analysis of a Subcritical Reactor Core with a MOX-Fuel using the Birth-and-Death Model
Nuclear Engineering and Technology
2021 .06
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
Study on Stiffened-Plate Structure Response in Marine Nuclear Reactor Operation Environment
한국해양공학회지
2023 .10
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .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
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
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