Zobrazeno 1 - 10
of 113
pro vyhledávání: '"Hai-Shan Zhou"'
Autor:
Wu-Qingliang Peng, Yu-Ping Xu, Yu Tian, Huai-Zhi Li, Fang-Yong Du, Shou-An Puyang, Qiang Li, Hai-Shan Zhou, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101720- (2024)
Compared to CuCrZr, oxide dispersion strengthened copper alloy (ODS-Cu) exhibits higher stability of properties under irradiation and exposure to elevated temperatures, demonstrating broad application prospects in divertor components. Oxygen-free hig
Externí odkaz:
https://doaj.org/article/30b2e7f19ee34378944c8f3a39abf905
Autor:
Xiang Geng, Qiang Qi, Wu Wang, Tom Guo, Yubo Cai, Shouxi Gu, Qingjun Zhu, Hai-Shan Zhou, Songlin Liu, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101710- (2024)
This research aims to investigate the application of the hot pressing (HP) sintering process in the fabrication of W-B-Fe-Cr-C advanced shielding materials and analyze the relationship between their microstructure and mechanical properties. The findi
Externí odkaz:
https://doaj.org/article/01749649527944eb9f5fbb148abb9d01
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101708- (2024)
The stability of microstructure and functions under irradiation is a critical issue for tritium permeation barriers (TPBs). High-energy ion irradiation has been an ideal tool for studying the effects of irradiation on the hydrogen isotope permeation
Externí odkaz:
https://doaj.org/article/ef914c2bd6214709a18f207eefd8f013
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101701- (2024)
High boron steels containing 2 wt% and 3.3 wt% boron were fabricated using hot isostatic pressing (HIP). The enhanced shielding performance of the steel with higher boron content was quantitatively evaluated through Monte Carlo simulations using soft
Externí odkaz:
https://doaj.org/article/119d89dfc47148c19320eaf6d995ce36
Autor:
Zi-Han Tao, Hao-Dong Liu, Si-Xiang Zhao, Xue-Chun Li, Cai-Bin Liu, Yi-Wen Zhu, Chen Wang, Hai-Shan Zhou, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101694- (2024)
Copper-based brazing filler materials are commonly employed in vacuum brazing techniques to achieve joining of plasma-facing components for ITER. In this work, gas-driven permeation (GDP) and thermal desorption spectroscopy (TDS) experiments have bee
Externí odkaz:
https://doaj.org/article/ccb2603725af40c2b8e0b8a5b903c9fd
Autor:
Ya-Wen Li, Xiao-Chun Li, Bai-Chuan Xu, Yilang Mai, Wei Wu, Ziqi Li, Hai-Shan Zhou, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101771- (2024)
In this study, molecular dynamics (MD) simulations are employed to investigate the interactions between point defects and grain boundaries (GBs) in tungsten. Firstly, the segregation energy of vacancies (Vs) and self-interstitial atoms (SIAs) to GBs
Externí odkaz:
https://doaj.org/article/f15a1a281548408c9ac19be42d82174a
Autor:
Fang-Yong Du, Yu-Ping Xu, Yu Tian, Wu-Qingliang Peng, Zhen Chen, Qiang Li, Hai-Shan Zhou, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 39, Iss , Pp 101646- (2024)
In tokamak devices, tungsten (W), as the main candidate for plasma facing material, will suffer from the simultaneous challenges of high heat flux (HHF) and neutron irradiation. This study involved annealing experiments on W-3Re alloy using two disti
Externí odkaz:
https://doaj.org/article/86fcf58223a44d8c8164f0a9776b4b27
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101613- (2024)
With the development of fusion devices towards compact designs, the space available for shielding is more limited. So high performance shielding materials are urgently needed to meet the shielding requirements. W-B-Fe-Cr-C Reactive Sintered Borides (
Externí odkaz:
https://doaj.org/article/3c31e3eff2a242ac9574ecc05c201aa9
Autor:
Xue-Chun Li, Hai-Shan Zhou, Xin-Dong Pan, Cai-Bin Liu, Zi-Han Tao, Hao-Dong Liu, Guang-Nan Luo
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101598- (2024)
In future fusion reactors, W-Cu joining technology will be utilized to fabricate plasma facing components (PFCs). In this study, hydrogen isotope gas-driven permeation (GDP) and thermal desorption spectrometry (TDS) are performed for W-Cu, W and Cu s
Externí odkaz:
https://doaj.org/article/65697ce36f614816b536fd379550b7a2
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101574- (2024)
Alumina is considered as one of the most promising candidates for tritium permeation barrier. Coating preparation parameters such as the thickness and the surface coverage both affect the hydrogen isotope resistant performance of TPBs. Alumina coatin
Externí odkaz:
https://doaj.org/article/1e9fabdefa6b401eb9ee4c7f037f05ac