The effect of cold-work and stress-relieving on the irradiation growth behaviour of zirconium alloys

Author:

Fidleris V.

Publisher

Elsevier BV

Subject

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

Reference12 articles.

1. Properties of Reactor Materials and Effects of Radiation Damage;Buckley,1962

2. Radiation Damage in Reactor Materials I;Hesketh,1969

3. Application of the generalised theory of yielding creep to irradiation creep in Zirconium alloys

4. Non-linear growth in zircaloy-4

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3. Long-Term Irradiation Growth in Zirconium Alloys;Zirconium in the Nuclear Industry: 18th International Symposium;2018-01-01

4. Effect of microstructure and addition of alloying elements on hydriding kinetics of Zr–Nb-based alloys;International Journal of Hydrogen Energy;2015-12

5. Microstructure and texture evolution in commercial-purity Zr 702 during cold rolling and annealing;International Journal of Minerals, Metallurgy, and Materials;2014-08

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