Results 11 to 20 of about 757 (179)

Thermonuclear Fusion Reactor Plasma-Facing Materials under Conditions of Ion Irradiation and Plasma Flux [PDF]

open access: yesSymmetry, 2021
A review of experimental studies carried out at the NRC “Kurchatov Institute” on plasma-facing thermonuclear fusion reactor materials is presented in the paper. An experimental method was developed to produce high-level radiation damage in materials simulating the neutron effect by surrogate irradiation with high-energy ions. Plasma-surface interaction
Boris I. Khripunov   +2 more
openaire   +2 more sources

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   +2 more sources

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

On the lifetime of the first mirrors in the diagnostic systems of the international thermonuclear experimental reactor [PDF]

open access: yes, 2006
Plasma diagnostic systems will be necessary tools for the future success of the International Thermonuclear Experimental Reactor (ITER) both to better understand the physics involved in magnetically confined burning plasma and for the protection of the
Temmerman, Gregory de
core   +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

A brief summary of the progress on the EFDA tungsten materials program [PDF]

open access: yes, 2013
The long-term objective of the European Fusion Development Agreement (EFDA) fusion materials programme is to develop structural and armor materials in combination with the necessary production and fabrication technologies for reactor concepts beyond the ...
Giusepponi, S., Celino, M.
core   +3 more sources

Home - About - Disclaimer - Privacy