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Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials
ITER will use beryllium as a plasma-facing material in the main chamber, covering a total
surface area of about 620 m 2. Given the importance of beryllium erosion and co-deposition …
surface area of about 620 m 2. Given the importance of beryllium erosion and co-deposition …
Extreme materials environment of the fusion “fireplace”
SJ Zinkle, A Quadling - MRS Bulletin, 2022 - Springer
Commercial fusion energy will require an energy-producing fusion plasma core (the “fire”)
surrounded by an integrated engineering system (the “fireplace”). This article focuses on the …
surrounded by an integrated engineering system (the “fireplace”). This article focuses on the …
[HTML][HTML] Plasma-wall interaction impact of the ITER re-baseline
To mitigate the impact of technical delays, provide a more rationalized approach to the
safety demonstration and move forward as rapidly as possible to a reactor relevant materials …
safety demonstration and move forward as rapidly as possible to a reactor relevant materials …
Overview of the JET results in support to ITER
X Litaudon, S Abduallev, M Abhangi, P Abreu… - Nuclear …, 2017 - iopscience.iop.org
The European nuclear fusion research community has elaborated a Roadmap to the
realisation of fusion energy in which 'ITER is the key facility and its success is the most …
realisation of fusion energy in which 'ITER is the key facility and its success is the most …
Tritium removal from JET-ILW after T and D–T experimental campaigns
D Matveev, D Douai, T Wauters, A Widdowson… - Nuclear …, 2023 - iopscience.iop.org
Abstract After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the
ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a …
ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a …
Lithium, a path to make fusion energy affordable
A De Castro, C Moynihan, S Stemmley, M Szott… - Physics of …, 2021 - pubs.aip.org
In this tutorial article, we review the technological, physics, and economic basis for a
magnetic fusion device utilizing a flowing liquid lithium divertor (molten metal velocity in the …
magnetic fusion device utilizing a flowing liquid lithium divertor (molten metal velocity in the …
Wall conditioning in fusion devices with superconducting coils
T Wauters, D Borodin, R Brakel… - Plasma physics and …, 2020 - iopscience.iop.org
Wall conditioning is essential in tokamak and stellarator research to achieve plasma
performance and reproducibility. This paper presents an overview of recent conditioning …
performance and reproducibility. This paper presents an overview of recent conditioning …
[HTML][HTML] Preliminary estimates of tritium permeation and retention in the first wall of DEMO due to ion bombardment
R Arredondo, K Schmid, F Subba… - Nuclear Materials and …, 2021 - Elsevier
Tritium self-sufficiency presents a critical engineering challenge for DEMO, requiring efficient
breeding and extraction systems, as well as minimizing tritium losses to the surrounding …
breeding and extraction systems, as well as minimizing tritium losses to the surrounding …
A step towards the diagnostic of the ITER first wall: in-situ LIBS measurements in the WEST tokamak
As part of the development of proven diagnostics allowing the characterization of ITER's
PFUs (Plasma Facing Units) without dismantling, LIBS (Laser-Induced Breakdown …
PFUs (Plasma Facing Units) without dismantling, LIBS (Laser-Induced Breakdown …
Isotope removal experiment in JET-ILW in view of T-removal after the 2nd DT campaign at JET
T Wauters, D Matveev, D Douai, J Banks… - Physica …, 2022 - iopscience.iop.org
A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like
beryllium main chamber wall and tungsten divertor, to reduce the plasma deuterium …
beryllium main chamber wall and tungsten divertor, to reduce the plasma deuterium …