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Meeting 2019 TMS Annual Meeting & Exhibition
Symposium Mechanical Behavior of Nuclear Reactor Components
Sponsorship TMS: Nuclear Materials Committee
Organizer(s) Clarissa A. Yablinsky, Los Alamos National Laboratory
Assel Aitkaliyeva, University of Florida
Khalid Hattar, Sandia National Laboratories
Janelle P. Wharry, Purdue University
Laurent Capolungo, Los Alamos National Laboratory
Eda Aydogan, Los Alamos National Laboratory
Scope 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
Abstracts Due 07/16/2018
Proceedings Plan Planned: Supplemental Proceedings volume
PRESENTATIONS APPROVED FOR THIS SYMPOSIUM INCLUDE

A New RPV High Fluence Low Flux RPV Embrittlement Model for the International Surveillance Database
A Study on Tensile Behaviour and Microstructural Characteristics of Zircaloy-4 Processed through Swaging
Additively manufactured grade 91 steel for reactor applications
Amorphous intergranular films for improved performance under irradiation
An Overview of Small Scale Mechanical Property Measurements on Irradiated Steels
Analytical methodology to predict crack growth for irradiated stainless steel 304L under combined fatigue-creep loading
Austenitic oxide dispersion strengthened (ODS) steels: Insights into their microstructure and mechanical behavior
Characterization of creep-fatigue crack propagation in Alloy 709 at high temperatures using computational simulations and experimental testing
Combined nanomechanical and high-resolution microscopy to understand plasma-surface interactions in fusion energy materials
Compressive creep of porous γ-phase uranium metal
Continuum theory of defects and microstructure evolution under irradiation
Correlating small scale mechanical properties and microstructure of U-10wt%Mo/Zr fuels
Correlation between the microstructure of precipitations and their mechanical contributions with and without radiation damage
Creep-Fatigue Interaction of Fe-25Ni-20Cr austenitic stainless steel (Alloy 709)
Damage and fracture of nuclear materials under extreme conditions: from nuclear graphite to TRISO fuel particles
Damage evolution characterized with in situ ion beam irradiation transient grating spectroscopy
Deformation Behavior and Microstructural Evolution of Depleted Uranium - 10 wt% Molybdenum
Deformation mechanisms in a candidate FeCrAl alloy and its weldment after neutron irradiation
Development and Testing of Advanced Alloys for Very High Temperature and Dose Applications
Development of a Micropillar Compression Study for MAX Phases in Nuclear Applications
Directional Dependence of Irradiated Damage in W
Dose-dependent ductile to brittle transition temperature in ferritic polycrystalline aggregates: a 3D dislocation dynamics analysis
EBSD and High Resolution EBSD Analysis of Strain-Induced Phenomena in Irradiated Austenitic Steels
Effect of Friction Stir Welding on Microstructure Evolution on in situ and ex situ Self-Ion Irradiated MA956
Effects of irradiation on the kinetics of precipitation in Fe-Cr-C alloys
Evolution of Hardening during Irradiation: Nanoindentation and Nanostructural Characterisation Approach
Experimental and Modeling Study of Deformation Mechanisms in Irradiated ZIRLO
Experiments and Modeling of Mechanical Behaviour of Zircaloy-4 under Monotonic and Cyclic Loading for Research on Stress Corrosion Cracking
Grain Boundary Oxidation and Gas Release on Irradiated UO2
In-situ Observations of the Role of Stress-State on Strain to Failure of Non-hydrided and Hydrided Zircaloy-4
In situ micromechanical testing of He2+ ion irradiated Ni and Ni based superalloys for Gen IV nuclear reactors
In Situ TEM Clamped Beam Fracture of Irradiated Fe-9%Cr ODS
Interaction between the hydrogen retention and dislocation reconstruction in tungsten: a QM/MD study
Investigating the Effects of Existing Damage on Primary Damage Formation in Zirconium
Investigating the Effects of Wear in Reactor Environments using Ion Irradiation
Investigation of Radiation Temperature and Straining Temperature Effects on the Screw Dislocation Mobility Evolution in Irradiated Ferritic Grains Using 3D Dislocation Dynamics
Investigation of Susceptibility of A533B Steel to Temper Embrittlement
Irradiation Induced Creep in FCC Alloys Measured using in situ TEM
Irradiation Resistance of Advanced Ferritic/Martensitic Steel at High Irradiation Doses and Temperatures
Irradiation resistance of ARB processed CuNb nanolayered composites at very high doses and temperatures
Irradiation resistance of mechanically processed Zr-Nb multilayers at very high doses
Mechanical and Advanced Microstructural Analysis of Laser Beam Weldments Performed on Neutron-Irradiated 304 Austenitic Stainless Steel
Mechanical and microstructural characterization of three HT-9 heats (ORNL, LANL and EBR II) after side-by-side neutron irradiation at LWR and fast reactor relevant temperatures
Mechanical and Structural Transformation of Tungsten Implanted with He Ions
Mechanical and Thermal Behavior of Graphite in Nuclear Reactor Applications
Mechanical Properties and Microstructural Evaluation of a Pilgered Thin-walled OFRAC Tube for Fast Reactor Applications
Mechanical Properties of Tungsten Irradiated with a Thermal Neutron Shield
Mechanical Properties Retention of Accident Tolerant Fuel Cladding FeCrAl Alloys Following a Quenching Treatment.
Mechanical Property Changes in Ni-based Alloys with Long Range Order Formation
Micromechanical Investigation of Irradiation Effects in Beryllium
Micropillar compression of hydrogen containing Zircaloy-4 at temperatures to explore the performance of nuclear fuel cladding
Microstructural Evolution of High Density W-Cermets Exposed to Flowing Hydrogen at Temperatures Exceeding 2000 K
Multiscale Modeling for Nanoindentation of Zirconium Using an Atomistic-to-Continuum Coupling Method
Multiscale modeling of dislocation/precipitate interactions under cyclic loading
Multiscale modeling of radiation-induced Cu precipitation hardening in Fe-0.1at.%Cu
On The Elementary Deformation Mechanisms Involved In The Singular Behavior Of 15Cr-15Ni Fuel Cladding Tubes At Moderate Temperatures
On the Remarkable Fracture Toughness of 90 to 97W-NiFe Alloys Revealing Powerful New Ductile Phase Toughening Mechanisms
Procedures for the Interpolation of Orientation Distributions from Coarse Grid Experimental Measurements to Fine Grid Finite Element Meshes
Property-Property Correlations of Tensile, Shear-Punch, Hardness Measurements and Microstructure Property Relations from the UCSB ATR2 Experiment Database
Quantitative In-situ TEM Nanomechanical Testing of Model and Nuclear Relevant Engineering Alloys
Radiation effects on HT9 tempered martensitic steels as a function of nitrogen content and deformation
Strength and ductility enhancement of T91 ferritic/martensitic steel by partial tempering treatment
The effect of grain boundaries and second-phase particles on notch-tip hydride reorientation in zirconium alloys.
The Effect of Helium-Implantation on the Deformation Behaviour of Tungsten: X-ray Micro-Diffraction & Crystal-Plasticity
The Role of Non-Equilibrium Grain Boundary Structure in Radiation Tolerance and Thermal Stability
The Study of Mechanical Behaviour of Materials for the Nuclear Reactor Components in SUSEN Hot Cells
Thermal and Irradiation Climb in Discrete Dislocation Dynamics
Thermal Shock and in-situ Radial Strain Measurements
Thermomechanical Processing to Improve the Fracture Toughness of HT-9 Steels for High-Dose Applications
Towards Accurate Molecular Dynamics Simulations of Helium Bubble Nucleation in Palladium Tritide
Ultrastrong and ductile amorphous Si-O-C alloys
Understand the Phase Transformation and Mechanical Behavior of Thermally Aged and Neutron Irradiated Duplex Stainless Steels Using High-Energy X-ray Beamline Experiments
Understanding Deformation and Failure Mechanisms in Steels using High-Energy Synchrotron X-rays
Visco-Plastic Self Consistent (VPSC) Modeling of Deformation Processing of NFA-1 14YWT Thin-Walled Tubing


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