Full-Scale Fracture Toughness Behavior of Zr-2.5Nb Pressure Tubes with High Hydrogen Concentrations and Different Hydride Morphologies

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Symposium on Zirconium in the Nuclear Industry (19. : 2019 : Manchester) Zirconium in the nuclear industry
1. Verfasser: Cui, Jun (VerfasserIn)
Weitere Verfasser: Shek, Gordon K. (VerfasserIn)
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2021
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
The Creation of ZIRAT 2021 Rudling, Peter
Quantifying Processing Map Uncertainties by Modeling the Hot-Compression Behavior of a Zr-2.5Nb Alloy 2021 Daniel, Christopher S.
Corrosion and Ion Irradiation Behavior of Ceramic-Coated Nuclear Fuel Cladding 2021 Alat, Ece
The Behavior of Cr-Coated Zirconium Alloy Cladding Tubes at High Temperatures 2021 Chaari, Nermine
The Effect of Loading Direction on Slip and Twinning in an Irradiated Zirconium Alloy 2021 Thomas, Rhys
Measurement of In-Reactor Stress Relaxation in Preirradiated Zirconium Alloys by Four-Point Bend Technique 2021 Yagnik, Suresh
Photon Irradiation Effects on Oxide Surface Electrochemistry and Oxide Microstructure of Zircaloy 4 in High-Temperature Water 2021 Couet, Adrien
Influence of Thermomechanical Cycling on Prehydrogenated Zircaloy-4 Embrittlement by Radial Hydrides 2021 Desquines, Jean
Crystal Structure of Hydride Platelets in Hot Rolled Zircaloy-2, Characterized with Synchrotron X-Ray Diffraction, S/TEM, and EELS 2021 Badr, Nima Nikpoor
Characterization of Hydrides and the α-Zr Matrix in Zirconium Alloys: Effects of Stresses, Microstructure, and Neutron Irradiation on Hydride Texture, Terminal Solid Solubility, and Dislocation Structure 2021 Vizcaino, Pablo
Development of Thermokinetic Tools for Phase Transformation Studies of Zr Alloys for Both In-Service and LOCA Conditions 2021 Toffolon-Masclet, Caroline
Thoughts on the Needed Focal Areas in the Research and Understanding of In-Reactor Corrosion, Hydrogen Absorption, and Hydrogen Migration in Zirconium Alloys 2021 Kammenzind, Bruce F.
Effects of Cold Spray Chromium Coatings on the Properties of Zirconium Alloys 2021 Walters, Jorie L.
Deformation Mechanisms of Zirconium Alloys after Irradiation Studied by Dislocation Dynamics Simulations and In Situ Straining Experiments in TEM 2021 Onimus, Fabien
Toward an Improved Understanding of the Mechanisms Involved in the Increased Hydrogen Uptake and Corrosion at High Burnups in Zirconium Based Claddings 2021 Abolhassani, Sousan
Corrosion and Deuterium Pickup in Zr-2.5Nb: Twenty Years of In-Reactor Testing at the OECD Halden Boiling Water Reactor 2021 Nordin, Heidi M.
Fundamental Understanding of Nb Effect on Corrosion Mechanisms of Irradiated Zr-Nb Alloys 2021 Yu, Zefeng
Zirconium Hydride Precipitation and Dissolution Kinetics in Zirconium Alloys 2021 Lacroix, Evrard
Fabrication of E110 Alloy Fuel Rod Claddings from Electrolytic Zirconium Base with Removing Fluorine Impurity for Providing Resistance to Breakaway Oxidation in High-Temperature Steam 2021 Markelov, Vladimir A.
Full-Scale Fracture Toughness Behavior of Zr-2.5Nb Pressure Tubes with High Hydrogen Concentrations and Different Hydride Morphologies 2021 Cui, Jun
Alle Artikel auflisten