scispace - formally typeset
Open AccessJournal ArticleDOI

Fusion materials modeling: Challenges and opportunities

Reads0
Chats0
TLDR
In this article, the authors describe the challenges associated with modeling the performance of plasma facing component and structural materials in a fusion materials environment, the opportunities to utilize highperformance computing, and two examples of recent progress.
Abstract
The plasma facing components, first wall, and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National Academy of Engineering has recently ranked the quest for fusion as one of the top grand challenges for engineering in the 21st century. These challenges are even more pronounced by the lack of experimental testing facilities that replicate the extreme operating environment involving simultaneous high heat and particle fluxes, large time-varying stresses, corrosive chemical environments, and large fluxes of 14-MeV peaked fusion neutrons. Fortunately, recent innovations in computational modeling techniques, increasingly powerful high-performance and massively parallel computing platforms, and improved analytical experimental characterization tools provide the means to develop self-consistent, experimentally validated models of materials performance and degradation in the fusion energy environment. This article will describe the challenges associated with modeling the performance of plasma facing component and structural materials in a fusion materials environment, the opportunities to utilize high-performance computing, and two examples of recent progress.

read more

Content maybe subject to copyright    Report

Citations
More filters
Journal ArticleDOI

Designing Radiation Resistance in Materials for Fusion Energy

TL;DR: In this article, three fundamental options for designing radiation resistance are outlined: Utilize matrix phases with inherent radiation tolerance, select materials in which vacancies are immobile at the design operating temperatures, or engineer materials with high sink densities for point defect recombination.
Journal ArticleDOI

Materials research for fusion

TL;DR: Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission reactors as mentioned in this paper, and has been the subject of decades of worldwide research efforts underpinning the present maturity of the fusion materials research program.
Journal ArticleDOI

Irradiation hardening of pure tungsten exposed to neutron irradiation

TL;DR: In this paper, a dispersed barrier hardening model informed by the available microstructure data has been used to predict the hardness of pure tungsten samples irradiated in HFIR at 90-850°C to 0.03-2.2°C.
Journal ArticleDOI

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

TL;DR: Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides as mentioned in this paper.
Journal ArticleDOI

Theory of tokamak disruptionsa)

Allen H. Boozer
- 20 Apr 2012 - 
TL;DR: Theoretical guidance is needed on two disruption questions: (1) When is a tokamak operating in a metastable state in which loss of control is credible (avoidance question), and (2) What is the worst credible level of destructive effects when plasma control lost and how can these effects be mitigated (effects question).
References
More filters
Journal ArticleDOI

Solution and Diffusion of Hydrogen in Tungsten

TL;DR: In this paper, the authors used mass spectroscopic and ultrahigh vacuum techniques to investigate the solubility and diffusion of hydrogen in tungsten with high temperatures between 1100 and 2400 K. The authors derived the diffusion constants, D = 4.1×10−3×exp (−9000/RT) cm2/sec.
Journal ArticleDOI

Operating temperature windows for fusion reactor structural materials

TL;DR: In this paper, a critical analysis is presented of the operating temperature windows for nine candidate fusion reactor structural materials: four reduced-activation structural materials (oxide-dispersion-strengthened and ferritic/martensitic steels containing 8-12%Cr, V-4Cr-4Ti, and SiC/SiC composites), copper-base alloys (CuNiBe), tantalum base alloys, and molybdenum and tungsten alloys.
Journal ArticleDOI

Ab initio study of helium in α-Fe : Dissolution, migration, and clustering with vacancies

TL;DR: In this paper, density functional theory calculations have been performed to study the dissolution and migration of helium in ''ensuremath{\alpha}$-iron, and the stability of small helium-vacancy clusters ${\mathrm{He}}n}{V}_{m}$ ($n,$m=0$ to 4).
Journal ArticleDOI

Surface reactions during growth and erosion of hydrocarbon films

TL;DR: In this article, the chemical reactions and physical processes which occur at the surface of hydrocarbon films during deposition from low-temperature hydrocarbon plasmas are reviewed and a framework for understanding film growth is presented.
Journal ArticleDOI

The influence of helium on the bulk properties of fusion reactor structural materials

TL;DR: In this paper, a review of the mechanisms and the anticipated rates of helium generation in fusion materials are discussed; helium introduction techniques simulating fusion conditions are reviewed in some detail and the atomistic behaviour of helium in metals as well as the nucleation and growth of helium bubbles are briefly surveyed.
Related Papers (5)