Jonghun Yoon
Hanyang University · Materials Science
이 교수의 연구실은 방사선 차폐 소재, 특히 복합 산화물 유리 및 금속 기반 복합재료의 방사선 차폐 성능을 핵심으로 연구하고 있습니다. B2O3-Bi2O3 기반 유리 시스템을 중심으로 γ선 및 중성자 차폐 특성에 대한 정밀한 물리적 분석과 몰수기반 시뮬레이션(예: MCNPX, Geant4)을 융합한 연구를 수행하고 있으며, 핵시설 및 의료 분야의 안전한 방사선 차폐 솔루션 개발을 목표로 하고 있습니다.
Figures are computed from collected data and may differ slightly.
For five B2O3–Bi2O3 glasses, detailedly, γ, neutron, & proton, alpha, and electron (charged particles) shielding efficacies were assessed in this work. The crucial photon attenuating (interaction probabilities) parameter i.e., mass attenuation coefficient (μ/ρ) was calculated by Phy-X/PSD software and procured μ/ρ results have been verified through MCNPX, Geant4, & FLUKA codes μ/ρ findings from which a quality unanimity among them was noticed over an energy range of 15 KeV–15 MeV. Following μ/ρ
The growing demand for composite materials with improved properties is attracting a lot of attention from industries such as automotive, aerospace, military, aviation, and other manufacturing. Aluminium metal matrix composites (AMMCs), with various reinforcements such as continuous/discontinuous fibers, whiskers, and particulates, have captured the attention due to their superior tribological, mechanical, and microstructural characteristics as compared to bare Al alloy. AMMCs have undergone exte
For both the B<sub>2</sub>O<sub>3</sub>-Bi<sub>2</sub>O<sub>3</sub>-CaO and B<sub>2</sub>O<sub>3</sub>-Bi<sub>2</sub>O<sub>3</sub>-SrO glass systems, <i>γ</i>-ray and neutron attenuation qualities were evaluated. Utilizing the Phy-X/PSD program, within the 0.015-15 MeV energy range, linear attenuation coefficients (µ) and mass attenuation coefficients (μ/ρ) were calculated, and the attained μ/ρ quantities match well with respective simulation results computed by MCNPX, Geant4, and Penelope codes
Adequate shielding from ionizing radiations is essential in nuclear facilities because of such radiations’ adverse effects on humans in the event of unwanted or accidental exposure. In the current work, for four distinct compositions of B2O3-Li2O, Li2O-Na2O-K2O-B2O3, Gd2O3-SiO2-B2O3, and Bi2O3-Li2O-ZnO-B2O3 glass systems, neutron and γ-ray attenuation competencies combined with elastic features have been examined for feasible nuclear radiation protection purposes. ΣR (fast neutron removal cross-
Here we describe three cases of choledochal cyst involving the cystic duct or isolated dilatation of the cystic duct. All cases were visualised on MR cholangiopancreatography (MRCP) imaging. We report findings of ultrasonography, CT and MRCP. These cases are extremely rare; nine cases have been reported in the English-language literature. This anomaly was not included in Todani's classifications of choledochal cysts, a system that is accepted worldwide. We think that this variant anomaly will be
Against photon energies extending from 0.015 to 15 MeV, MCNPX, FLUKA and PHITS codes are operated to simulate mass attenuation coefficients (μ/ρ) for a total of ten B2O3-Bi2O3-Li2O glass compositions with added Bi2O3 amount from 10 to 55 mol% (5 mol% growth gradually) as a substitute for total (B2O3 + Li2O) mol% content. All the computed μ/ρ values correctness is examined by Py-MLBUF and WinXCOM programs’ μ/ρ outcomes and we found a good agreement among them. 55Bi2O3-35B2O3-10Li2O (mol%) glass h
For B2O3-Bi2O3-BaO glass system, γ, proton, alpha, electron, and neutron radiation shielding aspects were examined. Adopting Phy-X/PSD software, mass attenuation coefficients (μ/ρ) have been derived, and such μ/ρ quantities are in good unanimity with evaluated FLUKA, Geant4, and MCNPX codes corresponding μ/ρ end products. Equivalent atomic number and up to 40 mfp ‘buildup factors’ (utilizing G–P fitting procedure) were reckoned at ten distinct penetration depths. Deduced radiation protection eff
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