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RISS 인기검색어
- 검색키워드
- 저자 : Minxuan Ni (검색결과 2 건)
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Preparation and Properties of the Fast-Curing γ-Ray-Shielding Materials Based on Polyurethane
Minxuan Ni,Xiaobin Tang,Hao Chai,Yun Zhang,Tuo Chen,Da Chen 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.6
In this study, fast-curing shielding materials were prepared with a two-component polyurethane matrix and a filler material of PbO through a one-step, laboratory-scale method. With an increase in the filler content, viscosity increased. However, the two components showed a small difference. Curing time decreased as the filler content increased. The minimum tack-free time of 27 s was obtained at a filler content of 70 wt%. Tensile strength and compressive strength initially increased and then decreased as the filler content increased. Even when the filler content reached 60 wt%, mechanical properties were still greater than those of the matrix. Cohesional strength decreased as the filler content increased. However, cohesional strength was still greater than 100 kPa at a filler content of 60 wt%. The γ-ray-shielding properties increased with the increase in the filler content, and composite thickness could be increased to improve the shielding performance when the energy of γ-rays was high. When the filler content was 60 wt%, the composite showed excellent comprehensive properties.
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Pin Gong,Minxuan Ni,Hao Chai,Feida Chen,Xiaobin Tang 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.3
With a highly functional methyl vinyl silicone rubber (VMQ) matrix and filler materials of B4C, PbO, andbenzophenone (BP) and through powder surface modification, silicone rubber mixing, and vulcanizedmolding, a flexible radiation shielding and resistant composite was prepared in the study. The dispersionproperty of the powder in the matrix filler was improved by powder surface modification. BP was addedinto the matrix to enhance the radiation resistance performance of the composites. After irradiation, thetensile strength, elongation, and tear strength of the composites decreased, while the Shore hardness ofthe composites and the crosslinking density of the VMQ matrix increased. Moreover, the compositeswith BP showed better mechanical properties and smaller crosslinking density than those without BPafter irradiation. The initial degradation temperatures of the composites containing BP before and afterirradiation were 323.6 C and 335.3 C, respectively. The transmission of neutrons for a 2-mm thicksample was only 0.12 for an AmeBe neutron source. The transmission of g-rays with energies of 0.662,1.173, and 1.332 MeV for 2-cm thick samples were 0.7, 0.782, and 0.795, respectively
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