The Creation of ZIRAT

The Creation of ZIRAT

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Veröffentlicht in:International Symposium on Zirconium in the Nuclear Industry (19. : 2019 : Manchester) Zirconium in the nuclear industry
1. Verfasser: Rudling, Peter (VerfasserIn)
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Sprache:eng
Veröffentlicht: 2021
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Titel Jahr Verfasser
A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion” 2021 Preuss, Michael
Development of Cr-Al Coating on Zircaloy-4 for Enhanced Accident Tolerant Fuel 2021 Kim, Hyun-Gil
Back-Calculated Indentation Stress-Strain Curves from Small Scale Testing and Verification Using Finite Element Models: Application to Nanoindentation and Micropillar Compression Study of a Heavy Ion Irradiated Zr-2.5Nb Alloy 2021 Wang, Qiang
Test-Reactor Study of the Effect of Zirconia Coating of Inconel Spacer Cells on Shadow Corrosion 2021 Anghel, Clara
Influence of Hydrides upon the Fatigue Initiation Behavior of Irradiated Zircaloy-2 2021 Honniball, Peter D.
Evaluation of Neutron-Irradiated Additively Manufactured Zircaloy-2 2021 Partezana, Jonna M.
Investigating the Corrosion Behavior of Zircaloy-4 in LiOH under a Thermal Gradient and Two-Phase Flow Regime 2021 Hulme, Helen
Enhanced Hydrogen Uptake and Reaction Kinetics during Oxidation of Zircaloy-4 in Nitrogen-Containing Steam Atmospheres 2021 Grosse, Mirco K.
Zirconium-Applied Anisotropic Cluster Dynamics for Irradiation-Induced Defect Modeling in Presence of Hydrogen 2021 Brimbal, Daniel
Experimental Simulation of the Behavior of E110 Claddings under Accident Conditions Using Electrically Heated Bundles 2021 Hózer, Zoltán
The Importance of Substrate Grain Orientation on Local Oxide Texture and Corrosion Performance in α-Zr Alloys 2021 Armson, Samuel J.
Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation 2021 Frankel, Philipp
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
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