Ming YU

Dr. Ming YU

orcid

Research Focus & Metrics

Academic Career Length

10Years (2017-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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1 December 2017 in Fusion Engineering and Design
Verified
Journal Article
Open access
Kang WangKang Wang
Kang Wang
XZXiang Zan
Xiang Zan
MYMing YU
Ming YU
WPWolfgang Pantleon
Wolfgang Pantleon
LLLai-Ma Luo
Lai-Ma Luo
YWYucheng Wu
Yucheng Wu

1 December 2017 in Fusion Engineering and Design
Verified
Journal Article
Closed access
MYMing YU
Ming YU
KWKang Wang
Kang Wang
XZXiang Zan
Xiang Zan
WPWolfgang Pantleon
Wolfgang Pantleon
LLLaima Luo
Laima Luo
YWYucheng Wu
Yucheng Wu

1 February 2021 in IOP Conference Series: Earth and Environmental Science
Verified
Conference Paper
Open access
PDF file
XLXiaoling Li
Xiaoling Li
MYMing YU
Ming YU
XXXiaohui Xu
Xiaohui Xu
RWRongjun Wu
Rongjun Wu
This paper carried out an optimization design and application study on a high temprature resistant borated polyethylene shielding material, according to the nuclear power plant source characteristics and special protection requirements. The composition of borated polyethylene shielding material was optimized based on the genetic algorithm and Monte Carlo methods, then it was realized by blending modification and graft copolymerization to improve the high temperature resistant, shielding and mechanical properties. Finally, comprehensive properties such as mechanical, neutron shielding, irradiation resistance and high temperature resistance experiments were verified with the ordinary borated polyethylene and polypropylene. Those just proved the optimized borated polyethylene shielding material has excellent performance comparatively, especially it could keep complete structure in a high temperature environment up to 190°C during 48 hours, meeting the requirements of radiation protection safety for nulear power plant completely.

26 August 2025 in Polymers
Verified
Journal Article
Open access
PDF file
MYMing YU
Ming YU
FLFan Luo
Fan Luo
XLXiaoling Li
Xiaoling Li
XCXianglei Chen
Xianglei Chen
ZGZhirong Guo
Zhirong Guo
A novel high-temperature-resistant W-B4C-poly(4-methyl-1-pentene) (PMP) composite shielding material against neutron and gamma rays was developed and fabricated. Firstly, utilizing the 235U-induced fission spectrum as the source term, the compositional ratio of the W-B4C-PMP ternary composite was optimized using the genetic algorithm-based GENOCOPIII program coupled with MCNP simulations. Then, the composite was fabricated through coupling agent modification, melt mixing, and hot pressing. Finally, the effects of coupling modification and tungsten content on the thermomechanical properties of the composite were investigated. Results demonstrated that functional groups from the silane coupling agent KH550 were successfully grafted onto the filler surfaces. For composites containing 30 wt% modified B4C and 40 wt% modified W in the PMP matrix, the heat deflection temperature (HDT) increased by 18.5% and 19.1%, respectively, compared to their unmodified counterparts. The impact strength also improved by 31.6% and 5.0%, respectively. The variation trend of the composite’s modulus approximately followed the classical Einstein model, while its tensile strength and flexural strength conformed precisely to the model: σcσm=0.88Vf−0.02. Thermal analysis indicated that the composites possessed a melting point exceeding 230 °C, and their thermal stability improved with increasing filler content.