Nuclear Materials Committee

Technical Programming

2019 TMS Annual Meeting & Exhibition: Additive Manufacturing for Energy Applications: Organized by Isabella Van Rooyen; Subhashish Meher; Indrajit Charit; Somayeh Pasebani; Chad Duty

Additive manufacturing (AM) has emerged as a global disruptive technology in multiple industries for manufacturing complex three-dimensional components by the deposition of ceramics, alloys, or metal precursors within a variety of dimensional space. AM techniques provide a unique advantage for the energy industry due to the shortened development and fabrication times, quality of the product and repeatability of the process. Not yet commonplace in the energy sector, AM provides new opportunities in the design space during inception of new products (both structural component and material design) due to less limitations on localized design features that could not generally be performed using conventional fabrication processes (e.g., casting, extrusion, etc.) and subtractive fabrication. The advantage of using AM in energy applications will include, but not limited to, advancement in alloying, design and efficiency. This symposium will integrate invited and contributed talks on use of AM in various energy industries and includes the following topics based on experimental and computational approaches: • Property-microstructure-processing relationships of AM fabricated materials for structural components (e.g. 316 stainless steel) and fuel systems (e.g. U-Zr) in nuclear and other energy industries. • The scope of AM in nuclear energy enabling advanced sensor and instrumentation. • Advances in AM design concepts such as graded structures and post-processing treatments. • Modeling and simulations for design of high performance AM fabricated materials and reducing research time and costs. • Development and Qualification approaches.

2019 TMS Annual Meeting & Exhibition: Ceramic Materials for Nuclear Energy Research and Applications : Organized by Yongfeng Zhang; Xian-ming (David) Bai; David Andersson; Thierry Wiss

Nuclear energy is an essential element of a clean energy strategy, avoiding greenhouse gas emissions of over two billion tons per year. Ceramic materials play a critical role in nuclear energy research and applications. Nuclear fuels, such as uranium dioxide (UO2) and mixed oxide (MOX) fuels, have been widely used in current light water reactors (LWRs) to produce about 15% of the electricity in the world. Silicon carbide (SiC) is a promising accident-tolerant cladding material and is under active research studies. Some oxide ceramics have been proposed for novel inert matrix fuels or have been extensively studied as waste forms for the immobilization of nuclear waste. Moreover, ceramics are under active studies for fusion reactor research. This symposium focuses on experimental and computational studies of ceramics for nuclear energy research and applications. Both practical reactor materials and surrogate materials are of interest. Topics of interest include: defect production and evolution; mobility, dissolution, and precipitation of solid, volatile, and gaseous fission products; changes in various properties (e.g., thermal conductivity, volume swelling, mechanical properties) induced by microstructural evolution; and radiation-induced phase changes. Experimental studies using various advanced characterization techniques for characterizing radiation effects in ceramics are of particular interest. The irradiation techniques such as laboratory ion beam accelerators, research and test reactors, as well as commercial nuclear power reactors are all of interest. Computational studies across different scales from atomistic to the continuum are all welcome. Contributions focused on novel fuels such as doped UO2, high-density uranium fuels like uranium nitrides and silicides, and coatings for accident-tolerant fuel claddings are also encouraged. This symposium is intended to bring together national laboratory, university, and nuclear industry researchers from around the world to discuss the current understanding of the radiation response of ceramics through experiment, theory, and multi-scale modeling. Some focused topic areas will be: " Experimental characterization of non-irradiated and irradiated oxide ceramics " Multi-scale modeling on microstructure evolution and physical properties in ceramics " Thermal-mechanical properties of oxides for nuclear energy " Non-oxide ceramics for nuclear energy

2019 TMS Annual Meeting & Exhibition: Materials for Molten Salt Energy Systems: Organized by Stephen Raiman; Jinsuo Zhang; Kumar Sridharan; Judith Vidal; Michael Short

The use of molten salts as a coolant in molten salt reactors (MSR) offers many advantages including low operating pressures, high temperatures, and favorable heat transfer. For concentrating solar power systems (CSP), the use of molten salts as a heat transfer medium enables efficient thermal energy storage. Despite the advantages, the highly aggressive molten salts present a challenging environment for salt facing materials. Further, the high temperatures presented by these systems require exceptional mechanical properties. This symposium covers structural and moderator materials in molten salt for nuclear power and concentrating solar power. Abstracts are solicited in the following topics: - Corrosion of salt-facing materials - Salt effects in graphite and moderator materials - Fission product embrittlement - Alloy selection and design for molten salt applications - Interaction of fission products with materials - Mechanical and creep properties - Salt chemistry effects on materials including radiolysis - Heat exchanger design - Welding and cladding issues - Waste handling and actinide recovery

2019 TMS Annual Meeting & Exhibition: Mechanical Behavior of Nuclear Reactor Components: Organized by Clarissa Yablinsky; Assel Aitkaliyeva; Khalid Hattar; Janelle Wharry; Laurent Capolungo; Eda Aydogan

Current and future generation nuclear reactors require improved structural materials that improve efficiency during in-service conditions, allow for long reactor lifetimes, and increase safety during accidents. Given the increasingly large number of reactor design being considered (e.g. fusion, molten salt, LWRs, etc.), a series of distinct material concepts have been proposed to address these needs. Effects of reactor environments on mechanical behavior will be a key component to predicting strength and performance of materials in the aforementioned circumstances. This symposium aims to take a closer look at the mechanical behavior of reactor components across length scales. With recent advancements and increased use of in-situ techniques, more is known about irradiation effects on strength than ever before. Simultaneously, ex-situ techniques are critical to probe component-sized parts, and validate the use of a material for inclusion within a reactor. Furthermore, synergy with materials modeling is advancing the prediction of material performance under normal and accident conditions, as well as reactor lifetimes. Topics of interest include, but are not limited to: • Mechanical behavior testing, including tension, compression, bend, bulge, creep, fatigue, and fracture • Effects of environment on strength, including dose, dose rate, temperature, and corrosion • Hardness testing, including nanohardness and microhardness • Development of microstructure sensitive material strength models • Modeling and simulation of irradiation defect interactions during mechanical testing • Macroscopic component modeling for full scale performance • In-situ mechanical testing, including micromechanical and nanomechanical compression and tension • Novel techniques to probe material strength under reactor conditions

2018 TMS Annual Meeting & Exhibition: Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling: Organized by James Cole; Peter Hosemann; Julie Tucker; Elaine West

The response of fuels and materials to radiation is critical to the performance of advanced nuclear systems. Key to understanding material performance in a nuclear environment is the analysis of materials irradiated using test reactors and ion beam facilities. This symposium will focus on recent results produced from irradiation programs around the world and will cover fundamental and applied science aspects of accelerated nuclear materials testing for fission and fusion reactors. Presentations combining experiment with theory, modeling and simulation to enhance our understanding of radiation induced degradation in materials are especially encouraged. Abstracts are solicited for (but not limited to) the following irradiation program topics: - Fundamental science of radiation damage and defect processes - Mechanical and fracture behavior of irradiated materials - Current and advanced nuclear fuels - Current and advanced structural materials - Fluence effects in materials

2018 TMS Annual Meeting & Exhibition: Accident Tolerant Fuels for Light Water Reactor: Organized by Lingfeng He; Andrew Nelson; Kumar Sridharan; Peng Xu

This symposium is focused on nuclear fuels with enhanced accident tolerance for Light Water Reactor (LWR) with an emphasis on assessment of their performance. Topics related to design, fabrication, characterization, irradiation, post-irradiation examination, testing simulating accident conditions, and modeling/simulation of accident tolerant fuels are within the scope of this symposium. This symposium will provide a platform for exhibiting and discussing recent experimental and computational progress in this area. Abstracts are solicited in (but not limited to) the following topics: • Accident tolerant fuel and cladding materials development • Microstructure, mechanical, thermodynamic and physical property characterization • Radiation damage and post-irradiation examination on accident tolerant fuel and cladding materials • Fuel rod, fuel cladding and component materials behaviors under accident conditions (corrosion, steam corrosion, chemical interaction, etc.) • Multi-scale modeling/simulation of materials behavior under normal and accident conditions

2018 TMS Annual Meeting & Exhibition: Atom Probe Tomography for Advanced Characterization of Metals, Minerals and Materials: Organized by Haiming Wen; Simon Ringer; Gregory Thompson; Arun Devaraj; Keith Knipling; Gang Sha; David Seidman; Chantal Sudbrack

Atom probe tomography (APT), is an emergent characterization technique that is capable of determining the chemical identity of each individual atom and generating 3D chemical maps imaging the distribution of individual atoms. The technique offers high spatial resolution (better than 0.3 nm achievable in all directions) and high analytical sensitivity (as good as 1 appm). APT provides information on elemental composition of the specimen, 3D visualization of distribution of atoms, composition of phases, morphology and size of precipitates, and solute distribution across interfaces, at grain boundaries and along dislocations. In many APT analyses, crystallographic information has been retained within the data, with the potential to directly relate the composition of specific microstructural features to their crystallography with unprecedented sensitivity and resolution. APT can be utilized in many different fields for advanced imaging and analysis of metals, minerals and materials, despite some limitations. This symposium is designed to bring together scientists, engineers and technicians from across disciplines to discuss the technique of APT, its applications and limitations. The symposium will encompass research and applications spanning a wide variety of topics. Presentations on experimental, theoretical, and modeling research are solicited. Topics for this symposium include, but are not limited to:  Applications of APT in advanced characterization of metals, minerals and materials  3D reconstruction and data analysis  Impact of specimen and instrument parameters and optimization of acquisition conditions  Specimen preparation techniques  Limitations of APT  Progress in APT technique  Correlative techniques

2018 TMS Annual Meeting & Exhibition: Computational Materials Science and Engineering for Nuclear Energy: Organized by Haixuan Xu; Michael Tonks; Blas Uberuaga; James Morris

This symposium will highlight current computational materials science and engineering efforts for nuclear reactors in the United States and abroad. High neutron flux, thermal and chemical gradients, and corrosive environments cause significant degradation in the chemical and mechanical properties of materials. Enhanced radiation resistance of structural materials and nuclear fuels are needed to overcome technological challenges necessary for future nuclear systems. This symposium seeks abstracts that apply�atomistic and mesoscale simulations to discover, understand, and engineer the macroscale performance of fission/fusion reactor materials, including fuel, cladding, and structural materials. This symposium will also consider multiscale modeling efforts that bridge length and time scales in order to better connect simulation results with experimental data for predictive model validation. It will also highlight validation of all relevant models, as well as uncertainty quantification. Finally, the application of ICME approaches to use modeling and simulation to better understand structure-property relationships, their associated links with performance, and their application to designing future reactor concepts and materials is also desired. Some examples include: • Modeling and simulation of materials behavior under extreme environments – radiation, corrosion, stress and temperature, including radiation effects, phase stability, fuel-clad interactions, fission product behavior. • Modeling and simulation of model materials to uncover fundamental behavior�that affects material performance in radiative environments. • Developing improved material models for LWR fuel and cladding. • Modeling and simulation of new fuel materials including metal, silicide, and nitride fuels. • Modeling and simulation of new cladding materials, such as silicon carbide, coated zirconium alloys, or FeCrAl. • Development and integration of computational tools, methods, and databases for reactor structural material design. Uncertainty quantification and validation of all the applications listed above.

2018 TMS Annual Meeting & Exhibition: Materials and Fuels for the Current and Advanced Nuclear Reactors VII: Organized by Ramprashad Prabhakaran; Dennis Keiser; Raul Rebak; Clarissa Yablinsky; Anne Campbell

Globally, significant efforts are ongoing to meet the growing energy demand with the increased use of nuclear energy. Extensive work is being performed to develop materials and fuels for the advanced nuclear reactors. In addition, efforts are also ongoing to extend the life of existing nuclear power plants. Scientists, engineers, and students at various national laboratories, universities, and industries are working on a number of materials challenges for the nuclear energy systems. The objective of this symposium is to provide a platform for these researchers to congregate, exhibit and discuss their current research work, in addition to sharing the challenges and solutions with the professional community and thus, shape the future of nuclear energy. Abstracts are solicited in (but not limited to) the following topics: - Nuclear reactor systems - Advanced nuclear fuels - fabrication, performance, and design - Advanced nuclear fuels - properties and modeling - Advanced structural materials - fabrication, joining, properties, and characterization - Lifetime extension of reactors - nuclear materials aging, degradation, and others - Experimental, modeling, and simulation studies - Fundamental science of radiation-material interactions - Irradiation effects in nuclear materials - Materials degradation issues - stress corrosion cracking, corrosion, creep, fatigue, and others - Design of materials for extreme radiation environments - Radiation measurement techniques and modeling studies - Nuclear waste - disposal, transmutation, spent nuclear fuel reprocessing