Nanomechanics and nanometallurgy of boundaries
Abstract not provided.
Publications
Investigation of d-ZrH1.66/a-Zr interface in Zr-based cladding materials with aberration-corrected scanning transmission microscopy
Abstract not provided.
In-situ TEM Study of Cu and Ag Nanoparticle Interaction
Abstract not provided.
Experimental Measurements of Slip in BCC Metals
Abstract not provided.
An In situ TEM Study into the Deformation and Failure of Pure ECAP Al
Abstract not provided.
Deformation and failure of tantalum studied by in-situ observation
Abstract not provided.
Thermal stability of ion irradiated nanograined nickel films - revised
Abstract not provided.
Tracking the deformation evolution of polycrystals using EBSD
Abstract not provided.
Stability of Ion-Irradiated Nanograined Nickel Films
Abstract not provided.
Combining in-situ TEM Heating and Precession Electron Microscopy to Study Microstructural Evolution in Nanograined Ni Films
Abstract not provided.
Grain growth in nanotwinned copper in a liquid helium environment
Abstract not provided.
In situ TEM Observation of Plastic Deformation Process in Tantalum
Abstract not provided.
Nanoporous Metals for Prevention of Helium Bubble Formation in Pd Tritides
Abstract not provided.
Multiscale Experiments on Stress Projection Parameters in BCC Tantalum
Abstract not provided.
Rapid First-order Screening and Detailed In situ Microstructural Characterization of Advanced Cladding Materials
Abstract not provided.
Understanding Abnormal Grain Growth in Nanograined Nickel through the Combination of in situ TEM and Precession Microscopy
Abstract not provided.
In situ TEM ion irradiation and atmospheric heating of cladding materials
Materials Research Society Symposium Proceedings
Over the course of use, both in-service and during storage, fuel claddings for nuclear reactors undergo complex changes that can drastically change their material properties. Exposures to irradiation, temperature changes, and stresses, as well as contact with coolant, storage pool, and dry storage environments, may induce microstructural changes, such as formation of radiation defects, precipitate dissolution, and chemical segregation, that can ultimately result in failure of the cladding if pushed beyond its limit. In order to predict the performance of cladding in-service and during storage, understanding of the dominant processes related to these changes and their consequences is essential. In situ transmission electron microscopy (TEM) allows dynamic observation, at the nanoscale, of microstructural changes under a range of stimuli, making it an excellent tool for deepening our understanding of microstructural evolution in claddings. This proceeding presents details of the new in situ ion irradiation TEM and in situ gas cell TEM capabilities developed at Sandia National Laboratories. In addition, it will present the initial results from both systems investigating radiation tolerance of potential Generation IV cladding materials and understanding degradation mechanisms in Zr-based claddings of importance for dry storage. © 2012 Materials Research Society.
H uptake in Zircaloy Reactor Fuel Claddings Studied with ERD
Abstract not provided.
Grain-size scaling transitions in the fatigue behavior of ultrafine and nanocrystalline Ni-Fe
Proposed for publication in Advanced Materials.
Abstract not provided.
Hydride Formation in Cladding materials Studied via In-Situ Environmental Heating Transmission Electron Microscopy
Abstract not provided.
Evaluation of Microstructure-Slip Relationships in BCC Tantalum
Abstract not provided.
An Investigation of Grain Orientation and Strain Fields in BCC Tantalum
Abstract not provided.
The Morphology of Tensile Failure in Tantalum
Proposed for publication in Metallurgical and Materials Transactions A.
Abstract not provided.
Predicting Performance and Aging of Materials
Abstract not provided.
The hardness and strength of metal tribofilms: An apparent contradiction between nanoindentation and pillar compression
Acta Materialia
After sliding contact of a hard spherical counterface on a metal surface, the resulting wear scar possesses a complex microstructure consisting of dislocations, dislocation cells, ultrafine or nanocrystalline grains, and material that has undergone dynamic recovery. There remains a controversy as to the mechanical properties of the tribolayer formed in this wear scar. To investigate the properties of this thin layer of damaged material in single crystal nickel, we employed two complementary techniques: pillar compression and nanoindentation. In both techniques, the tests were tailored to characterize the near surface properties associated with the top 500 nm of material, where the wear-induced damage was most extensive. Pillar compression indicated that the worn material was substantially softer than neighboring unworn base metal. However, nanoindentation showed that the wear track was substantially harder than the base metal. These apparently contradictory results are explained on the basis of source limited deformation. The worn pillars are softer than unworn pillars due to a pre-straining effect: undefected pillars are nearly free of dislocations, whereas worn pillars have pre-existing dislocations built in. Nanoindentation in worn material behaves harder than unworn single crystal nickel due to source length reduction from the fine-grained wear structure. © 2011 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
Results 76–100 of 124