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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Effect of Heat Treatment on Radiation Shielding Properties of Concretes
방사선방어학회지
2018 .01
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
Nuclear Engineering and Technology
2024 .09
A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
방사선방어학회지
2016 .01
Influence of Boric Acid on Prepared of Blended Films with Poly(vinyl alcohol) and Poly(acrylic acid)
한국고분자학회 학술대회 연구논문 초록집
2016 .04
Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
Nuclear Engineering and Technology
2023 .01
Effect of Green Surfactant on Tribological Performance of Micro-Size Boric Acid Based Lubricant for Bearing Application
한국정밀공학회 학술발표대회 논문집
2016 .05
Shielding design and analyses of the cold neutron guide hall for the KIPT neutron source facility
Nuclear Engineering and Technology
2018 .01
Gd effect on microstructure and properties of the Modified-690 alloy for function structure integrated thermal neutron shielding
Nuclear Engineering and Technology
2023 .05
Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
Nuclear Engineering and Technology
2024 .02
Micro gadolinium oxide dispersed flexible composites developed for the shielding of thermal neutron/gamma rays
Nuclear Engineering and Technology
2023 .05
Thermal neutron albedo and flux for different geometries neutron guide
Nuclear Engineering and Technology
2019 .01
High alloyed new stainless steel shielding material for gamma and fast neutron radiation
Nuclear Engineering and Technology
2020 .01
폴리올과 붕산의 착화합물 형성원리를 이용한 수용액 중의 보론 제거에 관한 라만 분광학 연구
화학공학
2015 .01
Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
Nuclear Engineering and Technology
2017 .06
Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene
Nuclear Engineering and Technology
2024 .06
Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector
Nuclear Engineering and Technology
2024 .09
Monte-Carlo simulation for detecting neutron and gamma-ray simultaneously with CdZnTe half-covered by gadolinium film
Nuclear Engineering and Technology
2023 .03
Neutron/gamma scintillation detector for status monitoring of accelerator-driven neutron source IREN
Nuclear Engineering and Technology
2024 .05
A high-stability neutron generator for industrial online elemental analysis
Nuclear Engineering and Technology
2024 .04
Occupational radiation exposure control analyses of 14?MeV neutron generator facility: A neutronic assessment for the biological and local shield design
Nuclear Engineering and Technology
2020 .08
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