Assessment of annealing parameter approximations in zirconium alloys-Reference-Cited by-同舟云学术

Assessment of annealing parameter approximations in zirconium alloys

Published:2019-12 Issue: Volume:527 Page:151814
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Robson J.D.

Funder

EPSRC Programme

MIDAS – Mechanistic understanding of Irradiation Damage in Fuel Assemblies

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference18 articles.

1. Behavior and properties of Zircaloys in power reactors: a short review of pertinent aspects in LWR fuel;Garzarolli,1996

2. Nucleation and growth of intermetallic precipitates in Zircaloy-2 and Zircaloy-4 and correlation to nodular corrosion behavior;Maussner,1987

3. Microstructure and corrosion studies for optimized PWR and BWR Zircaloy cladding;Garzarolli,1989

4. Correlation between 400°C steam corrosion behavior, heat treatment, and microstructure of Zircaloy-4 tubing;Thorvaldsson,1989

5. Analytical approaches and experimental verification to describe the influence of cold work and heat treatment on the mechanical properties of Zircaloy cladding tubes;Steinberg,1984

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1. Analysis of mechanical properties of short pin PWR dummy post irradiation;AIP Conference Proceedings;2024

2. Influence of manufacturing processes on β-phase precipitates and corrosion properties of Zr-1Nb alloys;Journal of Nuclear Materials;2022-08

3. Temperature and time effects of post-weld heat treatments on tensile properties and microstructure of Zircaloy-4;Journal of Nuclear Materials;2021-08

4. Microstructures and Mechanical Properties of a Commercial Pure Zirconium during Rolling and Annealing at Different Temperatures;Advanced Engineering Materials;2020-11-08