Zobrazeno 1 - 10
of 1 151
pro vyhledávání: '"T Muroga"'
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101236- (2022)
A reliable technique for creating joints between tungsten (W) and Reduced Activated Ferritic/Martensitic (RAFM) steel with a pure-copper (Cu) interlayer (W/Cu/RAFM steel) has been explored for developing the heat removal component in the baffle and d
Externí odkaz:
https://doaj.org/article/2b1ab91c80c84b48ba473a81b2098817
Publikováno v:
Results in Materials, Vol 7, Iss , Pp 100116- (2020)
Improvement of brittle mechanical properties on plasma facing materials-tungsten (PFM-W) is required for development of advanced divertors. We have developed dispersion-strengthened (DS)-W-Ti alloys using a new process which is based on a combination
Externí odkaz:
https://doaj.org/article/28b68c1de88f48e49937c5751f572602
Publikováno v:
Nuclear Materials and Energy, Vol 16, Iss , Pp 168-174 (2018)
Yttria (Y2O3) dispersed copper alloys were fabricated by an in-situ process combining Mechanical Alloying (MA) and Hot Isostatic Pressing (HIP). In this process, CuO powder was added into Cu(Y) alloy powders halfway during mechanical alloying (MA). T
Externí odkaz:
https://doaj.org/article/2ddabd1b0f874617a89d943d4a15ed88
Publikováno v:
Nuclear Materials and Energy, Vol 16, Iss , Pp 123-127 (2018)
The mechanical durability and soundness of the several oxide coating materials used as the electrical insulator and tritium permeation barrier are important design parameters on an advanced liquid breeding blanket system. We tried to investigate the
Externí odkaz:
https://doaj.org/article/9bffb6707c904b8c98ec3a856dc4c014
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 17-22 (2018)
Advanced oxide dispersion strengthened copper alloys are promising structural materials for application in divertor system of future fusion reactors due to high irradiation resistance, high thermal conductivity, and good mechanical properties. In thi
Externí odkaz:
https://doaj.org/article/c061aff9ce254a8d97881f8d509e8170
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 447-450 (2016)
High-purity Y-doped V-4Cr-4Ti alloys (0.1–0.2wt. % Y), manufactured by the National Institute for Fusion Science (NIFS), were used for this study. Heavy-ion and fission-neutron irradiation was carried out at temperatures 673–873K. During the ion
Externí odkaz:
https://doaj.org/article/124dd88d71fe461392d28adf2fb5c21b
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 436-440 (2016)
Bead-on-plate electron beam welding in high vacuum atmosphere was applied to the plates of NIFS-HEAT-2 and CEA-J57 heats of V–4Ti–4Cr alloy. Effect of post-weld heat treatment (PWHT) in the temperature range 673–1273K on the hardness, impact to
Externí odkaz:
https://doaj.org/article/e47b13465aee4095bfeeaf5f9ffdb74b
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 455-458 (2016)
A new Cu-Al alloy was fabricated by a MA-HIP method for application to the heat sink materials of divertors. With the increase in MA time, the grain size and Vickers hardness decreased and increased, respectively. At MA time of 32hrs, the hardness of
Externí odkaz:
https://doaj.org/article/4a2722cc6c2f499c904da3ec7fe7ad44
Akademický článek
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Publikováno v:
To cite this article: T. Muroga, S. Fukada & T. Hayashi (2019) Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities, Fusion Science and Technology, 75:7, 559-574, DOI: 10.1080/15361055.2019.1603499
his paper provides an overview of Japanese fusion engineering research activities focusing on those being carried out by the National Institute for Fusion Science (NIFS) and Japanese universities (Universities). NIFS is promoting the Fusion Engineeri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::71630bc017b2eb495e0ec302f5367656
http://hdl.handle.net/10655/00012905
http://hdl.handle.net/10655/00012905