Dynamic Simulation of Materials Modification and Deuterium Retention in Tokamak Fusion Environment
نویسندگان
چکیده
The ability of plasma-facing materials (PFM) in fusion reactor to withstand subsequent erosion as well as deuterium and tritium accumulation depends on material properties, which will continuously be changed during reactor operation. Variation in plasma parameters, using various materials for coating of reactor walls, e.g., Be for the first wall and W and C for the divertor area, and the presence of gases/impurities in the chamber will result in subsequent PFMs surface modification that will seriously affect deuterium/tritium retention and recycling as well as plasma operation. We modeled tungsten surface evolution during reactor operation for ITER relevant parameters of ions energy, fluence, and composition. We used our ITMC-DYN Monte Carlo package for the self-consistent integrated simulation to predict the effect of edge plasma conditions and impurities concentration on deuterium deposition, diffusion, and trapping. Processes of ions/target interaction, physical and chemical erosion, particles diffusion, molecular recombination and desorption were benchmarked with recent experimental results. Relation between ions fluence and blistering in near-surface layers was studied. A study was also performed for carbon co-deposition as an enhancing factor for tungsten erosion and blistering. Implementation of surface segregation and particles diffusion in composite materials allowed correct understanding of surface evolution at different target temperatures.
منابع مشابه
Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks
Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy. The spherical tours (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as NSTX and higher toroidal beta regimes and improves the design of a po...
متن کاملModeling hydrogen isotope behavior in fusion plasma-facing components
Article history: Received 15 August 2013 Accepted 25 November 2013 Available online 28 November 2013 In this work, we focus on understanding hydrogen isotope retention in plasma-facing materials in fusion devices. Three common simulation methods are usually used to study this problem that includes Monte Carlo, molecular dynamics, and numerical/analytical methods. A system of partial differentia...
متن کاملA New Interpretation of Alpha- Particle-Driven Instabilities in Deuterium-Tritium Experiments on the Tokamak Fusion Test Reactor . A New Interpretation of Alpha- Particle-Driven Instabilities in Deuterium-Tritium Experiments on the Tokamak Fusion Test Reactor
متن کامل
Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall
Deuterium retention in the divertor tokamak ASDEX Upgrade is studied by surface analysis and gas balances. Comparing C and W plasma facing components, the deuterium content of deposits at the divertor plates is dropped by a factor of 13. At the outer divertor significant implantation into the W coating is found. Deposition at remote areas is reduced by a factor of 14. Gas balances for ITER rele...
متن کاملMolecular dynamics simulation of erosion and surface evolution of tungsten due to bombardment with deuterium and carbon in Tokamak fusion environments
The behavior of tungsten as plasma facing material in fusion environment is investigated using molecular dynamics simulation. Tungsten erosion and surface evolution is simulated during irradiation by carbon and deuterium ions. Non-cumulative pure carbon bombardment on crystal tungsten shows that substrate temperature does not affect carbon trapping rate, implantation depth, and tungsten sputter...
متن کامل