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Meeting 2021 TMS Annual Meeting & Exhibition
Symposium Composite Materials for Nuclear Applications
Presentation Title Irradiation Induced Forced Chemical Mixing and Local Hardening in Mechanically-processed Immiscible Zr/Nb Multilayers
Author(s) Madhavan Radhakrishnan, Thomas Nizolek, Daniel Savage, Marko Knezevic, Nan Li, Yongqiang Wang, Mukesh Bachhav, Boopathy Kombaiah, Nathan Mara, Osman Anderoglu
On-Site Speaker (Planned) Madhavan Radhakrishnan
Abstract Scope Past studies have shown that PVD-processed multilayers provide enhanced radiation damage mitigation due to interfaces-driven defects absorption. This work investigates the radiation resistance of bulk nanolayered zirconium-niobium composites subjected to high irradiation doses. Three Zr/Nb multilayers with individual layer thickness of 15-80nm were synthesized by accumulative-roll-bonding process. The multilayers were subjected to a dose of 82 dpa at 500°C using 7MeV Zr2+ ion beam. Cross-sectional TEM examination indicates that, in all multilayers, ion-irradiation has induced heterogeneous fragmentation of Zr, Nb layers and a chemically homogeneous mixed layer beneath the irradiated surface. The extent of sub-surface microstructural changes in multilayers agrees with the calculated damage profile. Light ion irradiation up to 1 dpa with He2+ ions was done to quantify the radiation defects-induced hardening in multilayers. The talk would focus on the correlation irradiation-induced local microstructural and compositional changes, and hardening response in layered structures using APT and micro-pillar compression tests.
Proceedings Inclusion? Planned:
Keywords Characterization, Composites, Nuclear Materials

OTHER PAPERS PLANNED FOR THIS SYMPOSIUM

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Conformal Tungsten Coatings for Cermet Nuclear Fuel Elements
Corrosion and TEM Analysis of CVD and PVD Coatings for BWR Accident Tolerant Fuel Cladding
Coupled Primary and Secondary Recrystallization in Single Tungsten Fiber-reinforced Tungsten Composites
Development of PVD Cr Coatings for Hydrothermal Corrosion Mitigation of SiC-SiCf Fuel Cladding in LWRs
Development of UN/UO2 Composite Fuels for LWR Applications
Enhanced Microstructural Stability of ARB-processed Cu/Nb Nanolayers Under Heavy Dose Ion Irradiation at Elevated Temperatures
Evaluation and Irradiation of 14YWT Capacitive Discharge Resistance Welds
Experimental Characterisation of the Variation of Local Residual Stresses in TRISO Coatings
Fabrication, Characterisation and Oxidation Resistance of an Innovative Composite Fuel: UN Microspheres Embedded in UO2 Matrix
Improved Techniques for Determining Local Thermal Transport in Composite Nuclear Fuels
Irradiation Induced Forced Chemical Mixing and Local Hardening in Mechanically-processed Immiscible Zr/Nb Multilayers
Mechanical Strength of Explosion Welded Thin Stainless-steel Cladding on Carbon Steel
Novel Fiber Fretting Technique for Tribological Properties of Composite Interphases
Opportunities for Nanostructured Tungsten Alloys in Composite Fusion Materials
Overview of the Westinghouse Accident Tolerant and High Burnup Fuel Program
Post-irradiation Examinations of TRISO Particles Corroded in Molten FLiBe Salt under Neutron Irradiation
Radiation Tolerance and Microstructural Changes of Nanocrystalline Cu-Ta Alloy to High Dose Self-ion Irradiation
SiGA SiC-SiC Composites Development for Accident Tolerant Fuel
Solving the Brittleness Problem of Tungsten - Tungsten Fibre-reinforced Tungsten Composites
Sub-critical Crack Initiation, Coalescence and Propagation in Nuclear Graphite Studied by High-speed Pink Beam Synchrotron Tomography
Synthesis and Irradiation Response of Hetero FeCr - Fe2O3 Interfaces
Tristructural Isotropic (TRISO) Fuel for High-Temperature, Passively-Safe Nuclear Reactors
Tungsten-based High and Medium Entropy Alloys and Composites for Nuclear Applications
Tungsten Fibre-reinforced Copper – A High-Conductivity, High-Strength Composite Material for Plasma-facing Component Applications
Understanding Defect Recovery and Accommodation and Their Implications on Mechanical Performance in Irradiated Nanocomposite Materials
Uranium Nitride Advanced Fuel: An Evaluation of the Oxidation Resistance of Coated and Doped Grains
Use of Carbon Fibre-reinforced Carbon in Wendelstein 7-X
W2C-reinforced Tungsten: A Promising Candidate for DEMO Divertor Material

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