Zobrazeno 1 - 10
of 1 211
pro vyhledávání: '"Nuclear graphite"'
Autor:
Stefania De Rosa, Elisabetta Colantoni, Paolo Branchini, Domizia Orestano, Antonio Passeri, Gianlorenzo Bussetti, Lisa Centofante, Stefano Corradetti, Martina Marsotto, Chiara Battocchio, Cristina Riccucci, Luca Tortora
Publikováno v:
Heliyon, Vol 10, Iss 12, Pp e32718- (2024)
Nuclear-grade graphite is a high-efficiency material, widely used for vacuum applications in nuclear reactors and accelerators as targets facing particle beams. In these contexts, graphite is often exposed to extreme thermal stresses altering its phy
Externí odkaz:
https://doaj.org/article/87220666993f47768cf01ad5fa3b96f1
Akademický článek
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Publikováno v:
Journal of Materials Research and Technology, Vol 27, Iss , Pp 3565-3578 (2023)
The fracture properties of nuclear graphite and their effects on the structural failure process threaten the integrity and safety of High Temperature Gas-cooled Reactor structures. This study aims to develop close-form solutions to determine the size
Externí odkaz:
https://doaj.org/article/c2ea3bea934c45658baa036499a43cae
Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 3, Pp 591-599 (2023)
Tensile strength of graphite is a crucial criterion in the design and structural integrity evaluation of graphite components in reactors. To investigate the tensile strength of domestic graphite, as well as the effect of specimen size, grain size and
Externí odkaz:
https://doaj.org/article/c4b447ae67024c37b9cee02ee0aaa78e
Publikováno v:
He jishu, Vol 47, Iss 4, Pp 040203-040203 (2024)
BackgroundWithin GEN-IV reactors, nuclear graphite plays a crucial role as both a moderator and reflector in an environment characterized by high temperatures and intense fast neutron irradiation. The exposure to fast neutron irradiation induces the
Externí odkaz:
https://doaj.org/article/84fb35faea66454081f5f5aed8dd087e
Akademický článek
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Publikováno v:
Yuanzineng kexue jishu, Vol 57, Iss 2, Pp 345-352 (2023)
In this study, nuclear grade graphite was irradiated by 1.08 MeV C4+ at room temperature and 180 ℃ to 0.02 dpa, 02 dpa and 2 dpa, respectively, using the 320 kV highly charged ion beam platform for multidiscipline researches of Institute of M
Externí odkaz:
https://doaj.org/article/63ac1d8f3cfd4a4687a212803d593c5a
Autor:
Wei Zhang, Hongwei Zhu, Zelin Gao, Taowei Wang, Wendurina, Gang Xu, Shu-Xian Hu, Xiaotong Chen, Bing Liu, Yaping Tang
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101448- (2023)
With the continuous growth of the fourth-generation nuclear reactor, the oxidation of irradiated graphite (i-graphite) has become a great concern worldwide in recent years, not only for the far-reaching significance in the treatment of i-graphite was
Externí odkaz:
https://doaj.org/article/8ebe80fdba9b416d8407fb4203151935
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101453- (2023)
This paper presents the results of studies of the mechanical properties and fracture characteristics of MPG-6 graphite in the unirradiated state and neutron-irradiated at high temperature. MPG-6 is considered as a material for future high-temperature
Externí odkaz:
https://doaj.org/article/5a783e5e12bf4d2da135929d9738a14d
Catalyzed oxidation of IG-110 nuclear graphite by simulated fission products Ag and Pd nanoparticles
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101438- (2023)
To evaluate the stability of nuclear materials in high temperature gas reactors under air ingress conditions, catalytic oxidation of IG-110 graphite by two simulated fission products, metallic Pd and Ag, was studied in oxidative atmosphere and at tem
Externí odkaz:
https://doaj.org/article/9553ca48bd0044039c1d8c8684361bc7