Grain boundary sinks in neutron-irradiated Zr and Zr-alloys-Reference-Cited by-同舟云学术

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Grain boundary sinks in neutron-irradiated Zr and Zr-alloys

Published:1988-10 Issue: Volume:159 Page:405-416
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Griffiths M.,Gilbert R.W.,Coleman C.E.

Publisher

Elsevier BV

Subject

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

Reference41 articles.

1. Irradiation growth of zirconium single crystals

2. M. Griffiths, C.D. Cann and R.C. Styles, unpublished work.

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2. Structure and stability of small self-interstitials clusters in zirconium;Acta Materialia;2024-04

3. Study of Dislocation Loops Growth in Zr–Sn–Alloys Under Neutron Irradiation by Rate Theory Modelling;METALLOFIZIKA I NOVEISHIE TEKHNOLOGII;2022-12-13

4. An approximate in-situ method for investigating irradiation damage of grain boundary;Nuclear Materials and Energy;2021-12

5. Stability of vacancy and interstitial dislocation loops in α-zirconium: atomistic calculations and continuum modelling;Journal of Nuclear Materials;2021-10

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