Irradiation growth in annealed and 25% cold-worked Zircaloy-2 between 353

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Irradiation growth in annealed and 25% cold-worked Zircaloy-2 between 353–673 K

Published:1988-07 Issue:2-3 Volume:154 Page:276-285
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Rogerson A.

Publisher

Elsevier BV

Subject

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

Reference14 articles.

1. An overview of microstructural and experimental factors that affect the irradiation growth behaviour of zirconium alloys;Fidleris,1987

2. ‘Breakaway’ growth in annealed Zircaloy-2 at 353 K and 553 K

3. BNES Conf. on Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys;Murgatroyd,1983

4. 〈〉 Component dislocations in annealed Zircaloy irradiated at about 570 K

5. Acceleration of creep and growth of annealed zircaloy-4 by pre-irradiation to high fluences

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1. A hybrid rate theory model of radiation-induced growth;Acta Materialia;2024-06

2. A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code;Nuclear Engineering and Design;2021-03

3. Irradiation Growth;Comprehensive Nuclear Materials;2020

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

5. Modeling of sink-induced irradiation growth of single-crystal and polycrystal zirconiums in nuclear reactors;Journal of Nuclear Materials;2016-01

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