Experimental Simulation of the Behavior of E110 Claddings under Accident Conditions Using Electrically Heated Bundles

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Symposium on Zirconium in the Nuclear Industry (19. : 2019 : Manchester) Zirconium in the nuclear industry
1. Verfasser: Hózer, Zoltán (VerfasserIn)
Weitere Verfasser: Nagy, Imre (VerfasserIn), Farkas, Róbert (VerfasserIn), Vér, Nóra (VerfasserIn), Horváth, Márta (VerfasserIn), Novotny, Tamás (VerfasserIn), Perez-Feró, Erzsébet (VerfasserIn), Király, Márton (VerfasserIn), Kis, Zoltán (VerfasserIn), Maróti, Boglárka (VerfasserIn), Szentmiklósi, László (VerfasserIn), Holecz, Péter (VerfasserIn), Auguszt, György (VerfasserIn), Gémes, György (VerfasserIn)
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2021
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
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
Ex Situ and In Situ Studies of Radiation Damage Mechanisms in Zr-Nb Alloys 2021 Liu, Junliang
High Resolution Mapping of Light Elements in Zirconium Oxide with SIMS 2021 Jones, Christopher
Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size 2021 Ensor, Brendan
Fracture of Gamma and Delta Hydrides during Delayed Hydride Cracking 2021 Hanlon, Sean M.
Analysis of the Corrosion Behavior of Vapor-Deposited CrN-Coated Zirconium under Normal Operation and Accident Scenarios 2021 Dever, Caitlin
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
A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion” 2021 Preuss, Michael
Alle Artikel auflisten