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Zirconium alloy
Coupled Thermomechanical Responses of Zirconium Alloy System Claddings Under Neutron Irradiation
Electromagnetic Evaluation of Hydrogen Content in Zr 2.5%Nb Alloy
Evaluate the Contribution of the Fuel Cladding Oxidation Process on The
5.03 Corrosion of Zirconium Alloys
High Temperature Oxidation of Zirconium Base Alloy in Steam
Surface Chemistry of Zirconium
Effect of Alloying Elements on Hydrogen Pickup in Zirconium Alloys
Towards an Understanding of Zirconium Alloy Corrosion
Zirconium Alloys in Nuclear Technology
Comparison of the Mechanical Properties and Corrosion Resistance of Zirlo and Other Zirconium Alloys
Chapter 5. Clad-Coolant Chemical Interaction
Zr Alloy Corrosion and Hydrogen Pickup
"Corrosion and Hydriding of Zircaloy Fuel Cladding
The Effect of Oxygen on Properties of Zirconium Metal
Structure and Properties of Al–0.6 Wt.%Zr Wire Alloy Manufactured by Direct Drawing of Electromagnetically Cast Wire Rod
Atf-Isg-2020-01
Hydrogen in Zirconium Alloys: a Review
Degradation and Failure Phenomena of Accident Tolerant Fuel Concepts Chromium Coated Zirconium Alloy Cladding
Top View
Delayed Hydride Cracking of Zirconium Alloy Fuel Cladding
ATOMIC ENERGY »"5Ä L'energie ATOMIQUE OFCANADA LIMITED Tibv DU CANADA LIMITÉE
Waterside Corrosion of Zirconium Alloys in Nuclear Power Plants
Experiments on Ignition of Zirconium-Alloy in Prototypical Pressurized Water Reactor Fuel Assemblies in a Spent Fuel Pool with Complete Loss of Coolant
The Preparation of Zr-Deuteride and Phase Stability Studies of the Zr-D System T. Maimaitiyilia, A. Steuwerb, C. Bjerkéna, J. B
Global Nuclear Fuel
ZIRCONIUM and HAFNIUM by James B
Determination of Zirconium Isotope Composition and Concentration For
Hydride Rim Formation in E110 Zirconium Alloy During Gas-Phase Hydrogenation
Environmental Analysis of Zirconium Alloy Production
2010/03/24-Comment (3) of Aladar
Advanced LWR Nuclear Fuel Cladding System Development Trade-Off Study
Or Hydrogen-Enriched and (Prior-) Phases of Zirconium Alloys
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding
AECL-11342 SIMS Studies of the Corrosion of Zirconium RL Tapping
Chapter 9 Research on Core Melt Accidents
Zirconium Alloy Data Sheet
Separation of Zr from Zr-2.5Nb by Electrorefining in Licl-Kcl
High-Temperature Thermodynamic Activities of Zirconium in Platinum Alloys Determined by Nitrogen-Nitride Equilibria
Nuclear Zirconium Alloy Market 2021-04
Recent Advances in Protective Coatings for Accident Tolerant Zr-Based Fuel Claddings
Hydrogen Charging, Hydrogen Content Analysis and Metallographic Examination of Hydride in Zirconium Alloys
Effect of Oxidation and Nitriding on The
Zirconium Alloy Powders for Manufacture of 3D Printed Articles Used in Nuclear Power Industry
Development of the Core Melt Accident
Hydride Blister Formation in Zirconium-Alloy Pressure Tube Materials
Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I
Zirconium Alloys
Zirconium and Zirconium Alloy Passivation Process
5.4. Retention and Cooling of Corium Inside and Outside the Reactor Vessel 5.4.1
The Technologies of Zirconium Production for Nuclear Fuel Components in Ukraine
Nuclear Steam Supply System of Ultimate Safety Tr-1000 Pb (Tr-1000Pbnsss)
Hydride Embrittlement in Zircaloy Components
Simulating the Behaviour of Zirconium-Alloy Components in Nuclear Reactors
Corrosion Mechanisms in Zirconium Alloys 2007
Effect of Hydrogen and Oxygen Content on the Embrittlement of Zr Alloys