Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions
Under the anticipated operating conditions for demonstration magnetic fusion reactors
beyond ITER, structural and plasma-facing materials will be exposed to unprecedented …
beyond ITER, structural and plasma-facing materials will be exposed to unprecedented …
Data on erosion and hydrogen fuel retention in Beryllium plasma-facing materials
G De Temmerman, K Heinola, D Borodin… - Nuclear Materials and …, 2021 - Elsevier
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 …
Review of hydrogen retention in tungsten
T Tanabe - Physica Scripta, 2014 - iopscience.iop.org
Although extensive studies on hydrogen (H) retention in tungsten (W) loaded by ion
implantation, plasma exposure and gas charging have been done, reported amounts of H …
implantation, plasma exposure and gas charging have been done, reported amounts of H …
Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks
VP Budaev - Physics of Atomic Nuclei, 2016 - Springer
Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
In-vessel dust and tritium control strategy in ITER
A baseline strategy for dust and tritium-inventory control and recovery in ITER has been
established and preparations are underway for its implementation. Limits on dust and tritium …
established and preparations are underway for its implementation. Limits on dust and tritium …
Preparing the scientific basis for an all metal ITER
R Neu, EUPWI Taskforce… - Plasma Physics and …, 2011 - iopscience.iop.org
The use of beryllium, carbon and tungsten as plasma-facing materials (PFMs) in ITER calls
for dedicated investigations on their behaviour under the expected particle and power loads …
for dedicated investigations on their behaviour under the expected particle and power loads …
Mechanism of hydrogen isotope exchange for tritium removal in plasma-facing materials: a multi-scale investigation
The safety of future fusion reactors is critically dependent on the tritium (T) retention in
plasma-facing materials. Hydrogen isotope (HI) exchange offers a method to redistribute HIs …
plasma-facing materials. Hydrogen isotope (HI) exchange offers a method to redistribute HIs …
Materials-related issues in the safety and licensing of nuclear fusion facilities
N Taylor, B Merrill, L Cadwallader, L Di Pace… - Nuclear …, 2017 - iopscience.iop.org
Fusion power holds the promise of electricity production with a high degree of safety and low
environmental impact. Favourable characteristics of fusion as an energy source provide the …
environmental impact. Favourable characteristics of fusion as an energy source provide the …
Wall conditioning for ITER: Current experimental and modeling activities
D Douai, D Kogut, T Wauters, S Brezinsek… - Journal of nuclear …, 2015 - Elsevier
Wall conditioning will be required in ITER to control fuel and impurity recycling, as well as
tritium (T) inventory. Analysis of conditioning cycle on the JET, with its ITER-Like Wall is …
tritium (T) inventory. Analysis of conditioning cycle on the JET, with its ITER-Like Wall is …
First results and surface analysis strategy for plasma-facing components after JET operation with the ITER-like wall
During the carbon wall operations of JET since 2001, an extensive post-mortem analysis
programme has been carried out under the JET Task Force Fusion Technology and a similar …
programme has been carried out under the JET Task Force Fusion Technology and a similar …