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A high-stability neutron generator for industrial online elemental analysis
Nuclear Engineering and Technology
2024 .04
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
Effect of Heat Treatment on Radiation Shielding Properties of Concretes
방사선방어학회지
2018 .01
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene
Nuclear Engineering and Technology
2024 .06
Study on the design and experimental verification of multilayer radiation shield against mixed neutrons and γ-rays
Nuclear Engineering and Technology
2020 .01
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
Optimization of shielding to reduce cosmic radiation damage to packaged semiconductors during air transport using Monte Carlo simulation
Nuclear Engineering and Technology
2020 .08
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
High alloyed new stainless steel shielding material for gamma and fast neutron radiation
Nuclear Engineering and Technology
2020 .01
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
Low dose radiation shielding compound manufacturing technology trend
대한기계학회 춘추학술대회
2019 .04
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
Attenuation Curves of Neutrons from 400 to 550 Mev/u for Ca, Kr, Sn, and U ions in Concrete on a Graphite Target for the Design of Shielding for the RAON In-flight Fragment Facility in Korea
Nuclear Engineering and Technology
2019 .01
몬테카를로 시뮬레이션을 통한 micro-CT의 차폐 물질 및 위치 최적화 연구
방사선산업학회지
2018 .01
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
효과적인 중성자 차폐를 위한 경량 연자성 물질 활용방안 연구
방사선산업학회지
2023 .03
Electron Accelerator Shielding Design of KIPT Neutron Source Facility
Nuclear Engineering and Technology
2016 .06
Influence of aluminum and vanadium oxides on copper borate glass: A physical/radiological study
Nuclear Engineering and Technology
2024 .08
Shielding analyses supporting the Lithium loop design and safety assessments in IFMIF-DONES
Nuclear Engineering and Technology
2023 .04
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