T. M. Rosseel National Lead, Materials Research, Light Water Reactor Sustainability Program Contact 865.574.5384 | ROSSEELTM@ORNL.GOV All Publications Light Water Reactor Sustainability Program Materials Pathway Technical Program Plan Quantification of in-grain lattice gradient in neutron irradiated 304L SS during deformation using insitu EBSD... Development of a Reconstruction Methodology Based on X-Ray Computed Tomography to Generate Realistic 3D Concrete Microstructures in MOSAIC Complexity of deformation mechanism in neutron-irradiated 304L austenitic stainless steel at microstructural scale Microstructural characterization of neutron irradiated mineral concrete aggregates An Atom Probe Tomography Study of the Through Wall Attenuation Effect on Cu-rich Precipitate Formation in a Reactor Pressure Vessel Steel MOSAIC: An Effective FFT-based Numerical Method to Assess Aging Properties of Concrete Microstructural characterization and assessment of mechanical properties of concrete based on combined elemental analysis techniques and Fast-Fourier transform-based simulations Analysis of Localized Deformation Processes in Highly Irradiated Austenitic Stainless Steel through In Situ Techniques Crystallographic orientation of orthorhombic aragonite using reflection generalized ellipsometry NEUTRON-IRRADIATION–INDUCED DAMAGE ASSESSMENT IN CONCRETE USING COMBINED PHASE CHARACTERIZATION AND NONLINEAR FAST FOURIER TRANSFORM SIMULATION Irradiation Effects on Reactor Concrete Structures Fuzzy logic model of irradiated aggregates Crystallographic orientation of uniaxial calcite and dolomite determined using reflection generalized ellipsometry Radiation-Induced Degradation of Concrete in NPPs Radiation-Induced Changes in Quartz, A Mineral Analog of Nuclear Power Plant Concrete Aggregates CURRENT STATUS OF THE CHARACTERIZATION OF RPV MATERIALS HARVESTED FROM THE DECOMMISSIONED ZION UNIT 1 NUCLEAR POWER PLANT The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates Characterization of Radiation Fields for Assessing Concrete Degradation in Biological Shields of NPPs The Plan for Post-Irradiation Examination of Zion Reactor Pressure Vessel Beltline Materials Review of the Current State of Knowledge on the Effects of Radiation on Concrete... Characterization of Radiation Fields in Biological Shields of Nuclear Power Plants for Assessing Concrete Degradationa... Characterization of Radiation Fields in Biological Shields of Nuclear Power Plants for Assessing Concrete Degradation... Recent Advances in Understanding Radiation Damage in Reactor Cavity Concrete... Machining Test Specimens from Harvested Zion RPV Segments for Through Wall Attenuation Studies Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Physical Sciences Directorate Materials Science and Technology Division Materials in Extremes Section Advanced Nuclear Materials Group
