William E Windes
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View article: Influence of pre-existing defects on thermal transport in nuclear graphite
Influence of pre-existing defects on thermal transport in nuclear graphite Open
Nuclear graphite is a critical material in high-temperature nuclear reactors due to its superior thermal and mechanical properties. The manufacturing process leaves multi-scale ‘pre-existing’ defects that can affect thermal transport chara…
View article: Current and Future Technological Issues Challenges for Nuclear Graphite Components
Current and Future Technological Issues Challenges for Nuclear Graphite Components Open
Historical and current data requirements for component qualification, as-manufactured graphite material properties, Irradiated & degraded material issues, code rules – Construction & Operation, status of current ASME code rules, progress i…
View article: Dynamic Deformation in Nuclear Graphite and Underlying Mechanisms
Dynamic Deformation in Nuclear Graphite and Underlying Mechanisms Open
Time-dependent deformation in nuclear graphite is influenced by the creation and migration of radiation-induced defects in the reactor environment. This study investigates the role of pre-existing defects such as point defect clusters and …
View article: Low-Temperature Annealing of Nanoscale Defects in Polycrystalline Graphite
Low-Temperature Annealing of Nanoscale Defects in Polycrystalline Graphite Open
Polycrystalline graphite contains multi-scale defects, which are difficult to anneal thermally because of the extremely high temperatures involved in the manufacturing process. In this study, we demonstrate annealing of nuclear graphite NB…
View article: DOE ART Graphite R&D Introduction
DOE ART Graphite R&D Introduction Open
Introduction of ART Graphite R&D to include oxidation activities, oxidation resistant graphite, model development, ASME component failure, ASME code development (design rules), ceramic composites, AGC update, molten salt intrusion, split-d…
View article: An In Situ transmission electron microscopy study on the synergistic effects of Au-ion irradiation and high temperature on nuclear graphite microstructure
An In Situ transmission electron microscopy study on the synergistic effects of Au-ion irradiation and high temperature on nuclear graphite microstructure Open
The combined effects of high-temperature and heavy-ion irradiation on Mrozowski cracks (MC) and nuclear graphite crystallographic dimensions have been studied using in situ heating and in situ ion-irradiation in the transmission electron m…
View article: Real-Time Observation of Nanoscale Kink Band Mediated Plasticity in Ion-Irradiated Graphite: An In Situ TEM Study
Real-Time Observation of Nanoscale Kink Band Mediated Plasticity in Ion-Irradiated Graphite: An In Situ TEM Study Open
Graphite IG-110 is a synthetic polycrystalline material used as a neutron moderator in reactors. Graphite is inherently brittle and is known to exhibit a further increase in brittleness due to radiation damage at room temperature. To under…
View article: ASME Code Development - Nonmetallics
ASME Code Development - Nonmetallics Open
ASME Code Development - Nonmetallics slides to include behavior models, licensing & code, graphite R&D Program, As-Fab'd Properties, Mechanisms and Analysis, and Irradiation. Discussion on where these fit into Irradiation behavior, Ceramic…
View article: Vendor Irradiation Capsule A quick summary and update
Vendor Irradiation Capsule A quick summary and update Open
Vendor Irradiation Capsule (VIC) update and summary. Includes what the VIC is, why it is needed, options, how data will be used, and what is concluded from using VIC. Also discusses realistic irradiation timelines, available MTRs and reali…
View article: DOE ART Graphite Program Intro Status 2023
DOE ART Graphite Program Intro Status 2023 Open
General description of the ART Graphite Program with Status for 2023. This includes list of staff members, and brief description of behavior models, licensing & code, graphite R&D, As-Fab'd Properties, Machanism and Analysis, Irradiation. …
View article: ASME Irradiation Model
ASME Irradiation Model Open
ASME Irradiation Model: How to deal with irradiation data in ASME code rules. Includes discussion on challenges to nuclear graphite, such as lack of sufficient irradiation data to qualify graphite for nuclear application for all grades and…
View article: Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite
Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite Open
Nuclear graphite has been used as a moderator material in nuclear reactor designs dating back to the first reactor to reach criticality, Chicago Pile 1, in 1942. In addition, it is anticipated to be used in the conceptual Generation four (…
View article: Summary of Vendor Irradiation Capsule Workshop Hosted at Oak Ridge National Laboratory, October 3-4, 2022
Summary of Vendor Irradiation Capsule Workshop Hosted at Oak Ridge National Laboratory, October 3-4, 2022 Open
The Department of Energy office of Nuclear Energy, Advanced Reactor Technology office tasked Idaho National Laboratory (INL), and Oak Ridge National Laboratory (ORNL) with hosting a set of two workshops. The primary purpose of these worksh…
View article: Accurate Dosimetry for Future Advanced Reactor Deployment and Operation
Accurate Dosimetry for Future Advanced Reactor Deployment and Operation Open
Accurate Dosimetry for Future Advanced Reactor Deployment and Operation from a customer's perspective. The main discussion points will be why we should be interested in this topic of nuclear renaissance, practical examples, and Dosimetry's…
View article: Session 4: ASME Code Rules
Session 4: ASME Code Rules Open
General review of code rules What do they cover. What they don’t. Underlying assumptions Probability of failure Material property parameters Stresses and loads Degradation What is NonmetallicsWork Group (NWG) doing? Failure in components R…
View article: Graphite Oxidation Behavior: NRC Graphite Behavior Model
Graphite Oxidation Behavior: NRC Graphite Behavior Model Open
Graphite microstructure and oxidation Graphite crystal structure and basal planes Reactive surface area sites Zig-zag and Arm-chair Pore microstructure effects Interconnectivity Reactivity and oxygen transport Oxygen-graphitereaction Not C…
View article: GIF-VHTR Materials (Graphite) Project Plan: Progress since September 2021
GIF-VHTR Materials (Graphite) Project Plan: Progress since September 2021 Open
¦1: Data, Design Methodology and Construction 1.1: Graphite Selection and Acquisition Strategy (Original tasks completed) 1.2: Graphite Properties (Virgin Materials) 1.3: Graphite Fracture Behaviour(Original tasks completed) 1.4: Graphite …
View article: Session 3: Irradiation and Thermal Stesses - NRC Graphite Behavior Model
Session 3: Irradiation and Thermal Stesses - NRC Graphite Behavior Model Open
Graphite anisotropic microstructure Graphite crystal structure and basal planes Response to irradiation and temperature C-axis and a-axis behavior The effect of porosity Nano-and micro-length scale Microscopic to macroscopic response Mater…
View article: Graphite Material Behavior: NRC Graphite Behavior Model
Graphite Material Behavior: NRC Graphite Behavior Model Open
Introduction to graphite Fabrication of graphite Unique features of nuclear grade graphite Providing the properties As-fabricated material properties of interest Thermal diff, thermal stability, mechanical strength, etc. General graphite b…
View article: Performance of Graphite Oxidation with Environment and Specimen Geometry
Performance of Graphite Oxidation with Environment and Specimen Geometry Open
Introduction -Motive for the study (a modest request) •Issues that must be considered -Pertinent oxidation background information •Three oxidation regimes -ASTM D7542 • The primary parameters for oxidation control -Energy of the System -At…