Zobrazeno 1 - 10
of 35
pro vyhledávání: '"Yongduo Sun"'
Publikováno v:
Journal of Materials Research and Technology, Vol 32, Iss , Pp 1310-1323 (2024)
Oxide-dispersion-strengthened (ODS) steels are candidate materials for application in advanced nuclear reactors. In this study, the low-cycle fatigue performances of 13Cr-ODS ferritic steel pipes were investigated at 600, 700, and 800 °C. Cyclic sof
Externí odkaz:
https://doaj.org/article/55e181a403f3456096c8860eea51a15c
Autor:
Ming Shu, Qin Zhou, Yuanhua Shen, Zhangjian Zhou, Pengfei Wang, Le Chen, Yongduo Sun, Jun Xiao
Publikováno v:
Journal of Materials Research and Technology, Vol 25, Iss , Pp 3728-3743 (2023)
The creep performance of 20Cr25NiNb austenitic steel through the addition of W, Mo, and B elements was investigated. W and Mo enhanced high temperature creep resistance primarily through solid solution strengthening σss and precipitation strengtheni
Externí odkaz:
https://doaj.org/article/ceb9d661029047b8a4773f320ac64e6b
Autor:
Yongduo Sun, Raymond Yokomi
Publikováno v:
BMC Research Notes, Vol 16, Iss 1, Pp 1-3 (2023)
Abstract Objectives Citrus yellow vein clearing virus (CYVCV) is an emerging disease that poses a significant threat to the citrus industry in California. In this study, the viral genomic RNA was isolated from Eureka lemon plants in the greenhouse ex
Externí odkaz:
https://doaj.org/article/24704c6e15f34197a459fa984edbe396
Publikováno v:
Frontiers in Materials, Vol 9 (2022)
In this paper, the performance degradation behavior of fuel cladding material 20Cr25NiNb for the British Advanced Gas Reactor (AGR) is reviewed in detail, which is a strong guideline for the material selection of supercritical carbon dioxide cooled r
Externí odkaz:
https://doaj.org/article/7b812819bcbb4067844242c5f142a074
Autor:
Ke Shi, Jian Yang, Qingsong Chen, Yongduo Sun, Wei Zhang, Kun He, Rui Tang, Zhien Ning, Jiali Liao, Yuanyou Yang, Ning Liu, Jijun Yang
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss , Pp 101033- (2021)
The corrosion characteristics of 12Cr2W2Mn Ferritic/martensitic (F/M) steel before and after Au-ions irradiation in static lead–bismuth eutectic (LBE) have been investigated at 400 °C for 100 h. The results show that the samples without irradiatio
Externí odkaz:
https://doaj.org/article/2a06a67021a641c398684acd67337a40
Publikováno v:
Metals, Vol 12, Iss 7, p 1114 (2022)
FeCrAl oxide dispersion strengthened (ODS) steels are an important kind of cladding material for accident-tolerant fuels. Their radiation resistance and mechanical properties are closely related to the grain size and dispersed second phases. In order
Externí odkaz:
https://doaj.org/article/cf586c0465e145b6bb58bd24b5a8ff8c
Autor:
Ruiqian Zhang, Beibei Jiang, Chang Pang, Xun Dai, Yongduo Sun, Wei Liao, Qing Wang, Chuang Dong
Publikováno v:
Metals, Vol 7, Iss 4, p 144 (2017)
It is expected that low-Sn Zr alloys are a good candidate to improve the corrosion resistance of Zr cladding alloys in nuclear reactors, presenting excellent corrosion resistance and high strength. The present work developed a new alloy series of Zr-
Externí odkaz:
https://doaj.org/article/db28a4971ade4a31ae516b4dfb8f5c78
Publikováno v:
In Nuclear Engineering and Technology June 2021 53(6):1924-1930
Publikováno v:
International Journal of Energy Research. 45:10226-10234
Autor:
Kun He, Rui Tang, Jian Yang, Yuanyou Yang, Wei Zhang, Qingsong Chen, Ke Shi, Ning Liu, Yongduo Sun, Jijun Yang, Jiali Liao, Zhien Ning
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss, Pp 101033-(2021)
The corrosion characteristics of 12Cr2W2Mn Ferritic/martensitic (F/M) steel before and after Au-ions irradiation in static lead–bismuth eutectic (LBE) have been investigated at 400 °C for 100 h. The results show that the samples without irradiatio