In-reactor tubular creep of Zircaloy-2 at 260 to 300 °C
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference24 articles.
1. Uniaxial in-reactor creep of Zirconium alloys
2. The in-reactor creep of cold-worked Zircaloy-2 and Zirconium-2.5 wt % niobium pressure tubes
3. Mechanisms for the in-reactor creep of Zirconium alloys
4. Application of the generalised theory of yielding creep to irradiation creep in Zirconium alloys
5. Theory of the creep of zircaloy during neutron irradiation
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