For the first time in nearly forty years, large-scale nuclear power is seeing a resurgence around the world. Unlike the first wave of nuclear power expansion, this time two things have changed: 1) A far wider spectrum of countries is considering nuclear power for the first time, and 2) The first wave of nuclear power startup companies, spanning the range of small modular reactors (SMRs), Generation IV (Gen IV) fission reactors, and small-scale fusion reactors has exploded onto the scene. These companies’ reactor designs, such as those by NuScale, Terrapower, Transatomic, General Fusion, and others, will face previously unseen challenges related to continued materials performance in environments more prone to materials degradation via new mechanisms of corrosion, high irradiation dose, and long-term mechanical degradation than any nuclear system seen before. The already established fusion projects, like ITER or the demonstration fusion power plant (DEMO) development program, in their assessment of materials issues have highlighted a number of issues critical to the success of such projects.
The focus of this symposium will be on materials to enable this next generation of nuclear fission or fusion reactors, which by virtue of their size, their operating principles, and the need for longer-term, safer performance, must meet previously unseen materials performance criteria with higher levels of certainty. Particular attention will be paid to materials experiments, simulations, and theory concerning performance in new Gen IV fission reactors, plasma-facing and first wall components for fusion systems, long-lived (60-100 year) light water reactors, and new, accident-tolerant fuel and cladding designs to improve existing and future nuclear reactor performance. Abstracts will be solicited both from industry, from chief technology and engineering staff who can speak broadly about requirements for advanced reactor materials, as well as from leading academics and national/international laboratory staff researching the science and engineering of advanced reactor materials performance and development.
This symposium is the 5th of a series of bi-annual symposia on materials for nuclear energy within MRS Fall meetings since 2008.
Materials development and performance in Generation IV fission reactors, including high-temperature gas, molten salt fuel and coolant, liquid metals, and supercritical fluids
Development and characterization of materials to withstand high amounts of radiation damage, simulation of high level of neutron damage using ion irradiation
Novel characterization techniques of materials behavior under irradiation, stress, corrosion, temperature including 3D tomography, in situ methods
Accident-tolerant fuel and cladding development for light water and other reactors
Plasma-surface interactions and materials for first-wall fusion applications
He and H effects, their synergy with radiation defects, and swelling
Long-term (>50 years) material degradation in nuclear systems
Modeling damage evolution and phase stability in fuel, structural and nanostructured materials
Direct simulation of experiments through multiscale modelling enabled by high performance computing
11月27日
2016
12月02日
2016
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