Results 11 to 20 of about 8,040 (171)

Simulation study on the thermal stress of W/316L stainless steel first wall material

open access: yesHe jishu, 2022
BackgroundDuring the service period of the first wall materials, the thermal stress in the material is one of the key issues restricingt the safety of the fusion reactor.PurposeThis study aims to clarify the influencing factors of thermal stress in the W/
LIU Ze   +5 more
doaj   +1 more source

First-principles study of hydrogen capture, solution and mechanical effects in transition metal tungsten alloy W-TM (V, Nb, Ta)

open access: yesJournal of Materials Research and Technology, 2023
Tungsten alloy as a candidate for plasma facing materials (PFMs) in thermonuclear fusion experimental reactor (Tokamak) is of great significance for the successful use of nuclear fusion.
Jia-Cheng Liang   +4 more
doaj   +1 more source

Quantification of the influence of the C, Cr and P contents on the permeability of hydrogen through Fe alloys

open access: yesNuclear Materials and Energy, 2022
Ferritic-martensitic steels are candidate materials for blanket structural components of future thermonuclear fusion reactors. However, the tritium inventory that can be retained in different components of the reactor and its ability to migrate through ...
I. Peñalva   +4 more
doaj   +1 more source

The periodic etching of tungsten surface induced by hydrogen ion irradiation

open access: yesHe jishu, 2021
BackgroundMetal tungsten (W) has a high melting point, low hydrogen solubility and high thermal conductivity. Therefore, it has been selected as one of the most promising plasma-facing materials for the future international thermonuclear experimental ...
XIE Jun   +6 more
doaj   +1 more source

THIN NITRIDE LAYERS AS PERMEATION BARRIERS

open access: yesActa Polytechnica CTU Proceedings, 2018
Permeation barriers represent one of the crucial fields in materials development for thermonuclear fusion. Primary objective of the barriers is to suppress the permeation of hydrogen isotopes (mainly tritium) from future thermonuclear fusion facilities ...
Jakub Veverka   +5 more
doaj   +1 more source

Tritium retention in plasma facing materials of JET ITER-Like-Wall retrieved from the vacuum vessel in 2012 (ILW1), 2014 (ILW2) and 2016 (ILW3)

open access: yesNuclear Materials and Energy, 2021
ITER-Like-Wall (ILW) project has been carried out at Joint European Torus (JET) to test plasma facing materials relevant to International Thermonuclear Experimental Reactor – ITER [1].
E. Pajuste   +4 more
doaj   +1 more source

Important problems of future thermonuclear reactors*

open access: yesNukleonika, 2015
This paper concerns important and difficult problems connected with a design and construction of thermonuclear reactors, which have to use nuclear fusion reactions of heavy isotopes of hydrogen, i.e., deuterium (D) and tritium (T).
Sadowski Marek J.
doaj   +1 more source

The Nuclear-Weapons Complex and Denuclearization of North Korea

open access: yesКонтуры глобальных трансформаций: политика, экономика, право, 2018
The result of the implementation of the DPRK’s nuclear weapons program was the creation and successful testing  of  a  thermonuclear  explosive device.
A. S. Diyakov
doaj   +1 more source

Challenges for plasma-facing components in nuclear fusion

open access: yesMatter and Radiation at Extremes, 2019
The interaction processes between the burning plasma and the first wall in a fusion reactor are diverse: the first wall will be exposed to extreme thermal loads of up to several tens of megawatts per square meter during ...
Jochen Linke   +6 more
doaj   +1 more source

Laser Pulse Effects on Plasma-Sprayed and Bulk Tungsten

open access: yesMetals, 2017
Tungsten (W) is considered a promising plasma-facing material for protecting the divertor of the ITER (International Thermonuclear Experimental Reactor).
Roberto Montanari   +4 more
doaj   +1 more source

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