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논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
Monte Carlo simulation and optimization of neutron ray shielding performance of related materials
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A Proposal on Evaluation Method of Neutron Absorption Performance to Substitute Conventional Neutron Attenuation Test
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Neutron irradiation impact on structural and electrical properties of polycrystalline Al2O3
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Effect of Heat Treatment on Radiation Shielding Properties of Concretes
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Electron Accelerator Shielding Design of KIPT Neutron Source Facility
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A feasibility study of the Iranian Sun mather type plasma focus source for neutron capture therapy using MCNP X2.6, Geant4 and FLUKA codes
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Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source
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Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene
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A high-stability neutron generator for industrial online elemental analysis
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Occupational radiation exposure control analyses of 14?MeV neutron generator facility: A neutronic assessment for the biological and local shield design
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A REVIEW OF NEUTRON SCATTERING CORRECTION FOR THE CALIBRATION OF NEUTRON SURVEY METERS USING THE SHADOW CONE METHOD
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Electrical characteristics and deep-level transient spectroscopy of a fast-neutron-irradiated 4H–SiC Schottky barrier diode
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An Assessment of the Secondary Neutron Dose in the Passive Scattering Proton Beam Facility of the National Cancer Center
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Neutron Calibration Field of a Bare 252Cf Source in Vietnam
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Neutron/gamma scintillation detector for status monitoring of accelerator-driven neutron source IREN
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Method of the known cross sections for calibration of the fast neutron spectrometer with a single-crystal stilbene based detector
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중성자 토모그래피를 위한 영상처리 자체코드 개발 연구
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A high-density gamma white spots-Gaussian mixture noise removal method for neutron images denoising based on Swin Transformer UNet and Monte Carlo calculation
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Characterization of a Neutron Beam Following Reconfi guration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements
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