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Title: Final Technical Progress Report on "Plasma Surface Interactions: Predicting the Performance and Impact of Dynamic PFC Surfaces"

Technical Report ·
DOI:https://doi.org/10.2172/2279204· OSTI ID:2279204

The objective of this project is to develop, and integrate, high-performance simulation tools capable of predicting plasma-facing component (PFC) operating lifetime and the impact of the evolving surface morphology of tungsten-based PFCs on plasma contamination, including the dynamic recycling of fuel species and tritium retention, in future magnetic fusion devices. Establishing a fundamental physical understanding and developing predictive capabilities of plasma-surface interactions (PSI) requires simultaneously addressing complex and diverse physics occurring over a wide range of length (Angstroms to meters) and time (femtoseconds to years) scales, as well as integrating extensive physical processes across the plasma–surface interface. This requires development of not only detailed physics models and computational strategies at each scale, but also algorithms and methods to couple them effectively in a way that can be robustly validated. Deploying these tools requires the continued development and coupling of leadership-scale computational codes to describe the boundary plasma and the evolving PFC surface, as well as a host of simulations that bridge disparate scales to address complex physical and computational issues at the plasma–surface interface in multi-component materials systems for magnetic fusion energy development beyond ITER. This project will enable discovery of the key physical phenomena controlling critical PFC performance issues, and the quantitative prediction of their impact on PFC performance during both steady-state and transient plasma conditions. Such phenomena include: (i) surface evolution in regions of either net erosion or net deposition; (ii) the impact of the evolving surface composition and roughness on the retention and recycling of hydrogenic fuel isotopes; (iii) the impact of dilute impurities on surface morphological evolution and plasma contamination; and (iv) the effects of high-energy neutron damage on surface properties that could influence helium/hydrogenic species retention and recycling. The outcome of this project will be a suite of coupled plasma and materials modeling tools, and a leadership class PFC simulator to predict PFC evolution and feedback to the boundary plasma both during steady-state plasma operation and transient events. Success in the proposed research tasks will enable the prediction of both plasma fueling and the sources of impurity contamination that impact core plasma performance, and will lay the foundation for understanding, designing, and developing the materials required to meet the performance objectives of future fusion reactors. Advanced capabilities for predictive modeling of plasma-facing component (PFC) surface morphological evolution and near-surface structural evolution are required for evaluation of tungsten (W) as a PFC in ITER’s divertor and improvement of its performance. Atomistically-informed, hierarchically developed and properly parameterized continuum-scale models that can efficiently access the spatiotemporal scales of PFC tungsten dynamical response enable such quantitative predictions of PFC structural and morphological evolution. Toward this end, the research conducted at UMass Amherst focused on the development of a materials property and defect interaction database that is required for constitutive modeling of the mechanical response of PFC tungsten and heat and mass transport in the near-surface region and on the surface of the PFC material, as well as the development and continuous upgrading of surface morphological evolution models which will improve significantly the predictive accuracy of our PFC tungsten evolution simulators. This effort is within the scale-bridging mission of the PSI-SciDAC center. Specific research tasks executed at UMass Amherst included: (1) Development of comprehensive databases for: (a) PFC tungsten mechanical, thermal, and transport properties (including elastic properties, mechanical strength, thermal conductivity, coefficient of thermal expansion, diffusion coefficients, and heats of transport); and (b) energetics of plasma-related defect interactions in the PFC near-surface region; (2) Incorporation of the above databases into constitutive models to determine the level of stress, as well as heat and species fluxes in PFC tungsten under plasma exposure conditions; (3) Developing and continuous upgrading of our hierarchical, atomistically-informed continuum-scale models of PFC surface evolution by incorporating additional physics modules (diffusion mechanisms, bubble dynamics) into the models; and (4) Computational implementation of the above databases, constitutive models, and upgraded surface dynamics in our simulators for predicting surface and near-surface dynamical response of PFC tungsten, from He retention to surface damaged (fuzz) layer growth as a function of fluence, under realistic plasma exposure conditions. The atomistic simulations involved in the database development employed state-of-the-art interatomic interaction potentials with excellent predictive capabilities. Our PSI-SciDAC kinetic Monte Carlo simulators, surface morphological evolution simulators, and the Xolotl PFC simulator are properly upgraded by integrating into their capabilities the above property database, constitutive information, and additional physics modules (from surface diffusion mechanisms to subsurface bubble dynamics).

Research Organization:
University of Massachusetts Amherst
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR)
Contributing Organization:
University of Tennessee Knoxville; Oak Ridge National Laboratory; University of Missouri Columbia; Clemson University; Pacific Northwest National Laboratory
DOE Contract Number:
SC0018421
OSTI ID:
2279204
Report Number(s):
DE-SC0018421
Resource Relation:
Related Information: See related identifiers/DOIs below.
Country of Publication:
United States
Language:
English

References (22)

Corrigendum and Addendum: Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations (2019 Nucl. Fusion 59 066035) journal October 2020
Effects of elastic softening and helium accumulation kinetics on surface morphological evolution of plasma-facing tungsten journal November 2020
Helium segregation and transport behavior near ⟨100⟩ and ⟨110⟩ symmetric tilt grain boundaries in tungsten journal June 2018
Helium bubble size effects on the surface morphological response of plasma-facing tungsten journal July 2023
Hole formation effect on surface morphological response of plasma-facing tungsten journal May 2021
Helium flux effects on bubble growth and surface morphology in plasma-facing tungsten from large-scale molecular dynamics simulations journal May 2019
Strain Effects on the Diffusion Properties of Near-Surface Self-Interstitial Atoms and Adatoms in Tungsten journal July 2021
Effects of surface vacancy-adatom pair formation on PFC tungsten surface morphological response journal January 2023
Elastic Properties of Plasma-Exposed Tungsten Predicted by Molecular-Dynamics Simulations journal April 2020
Impact of Soret effect on hydrogen and helium retention in PFC tungsten under ELM-like conditions journal June 2023
Non-dilute helium-related defect interactions in the near-surface region of plasma-exposed tungsten journal October 2020
Onset of fuzz formation in plasma-facing tungsten as a surface morphological instability journal November 2021
Molecular-Dynamics Analysis of the Mechanical Behavior of Plasma-Facing Tungsten journal January 2023
Equation of state for He bubbles in W and model of He bubble growth and bursting near W{100} surfaces derived from molecular dynamics simulations journal June 2023
Theoretical Model of Helium Bubble Growth and Density in Plasma-Facing Metals journal February 2020
Thermal gradient effect on helium and self-interstitial transport in tungsten journal December 2021
Prediction of temperature range for the onset of fuzz formation in helium-plasma-implanted tungsten journal August 2020
Effect of helium flux on near-surface helium accumulation in plasma-exposed tungsten journal November 2021
Thermal expansion of plasma-exposed tungsten journal November 2022
Atomic-scale modeling toward enabling models of surface nanostructure formation in plasma-facing materials journal March 2019
Large-scale atomistic simulations of low-energy helium implantation into tungsten single crystals journal February 2018
On the origin of ‘fuzz’ formation in plasma-facing materials journal July 2019