A model to describe the irradiation-induced dimensional changes in polycrystalline graphites and carbons
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference12 articles.
1. Relationship between Preferred Orientation, Thermal Expansion, and Radiation‐Induced Length Changes in Graphite
2. A model to describe neutron-induced dimensional changes in pyrolytic carbon
3. Preferred orientation and its effect on bulk physical properties of hexagonal polycrystalline materials
4. A method for determining the degree of orientation of graphite
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1. On the contribution of local anisotropic creep to macroscopic irradiation-induced growth in zirconium alloy polycrystals;Philosophical Magazine;2024-09
2. The effect of thermal oxidation on the coefficient of thermal expansion of nuclear graphite;Journal of Materials Science;2020-03-27
3. Radiation and Thermomechanical Degradation Effects in Reactor Structural Alloys;Structural Alloys for Nuclear Energy Applications;2019
4. Characterisation of the anisotropy of pyrolytic carbon coatings and the graphite matrix in fuel compacts by two modulator generalised ellipsometry and selected area electron diffraction;Carbon;2012-02
5. Polycrystalline effects on irradiation creep and growth in textured zirconium;Journal of Nuclear Materials;1985-04
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