The stress dependence for high temperature creep of polycrystalline uranium dioxide-Reference-Cited by-同舟云学术

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The stress dependence for high temperature creep of polycrystalline uranium dioxide

Published:1970-03 Issue:3 Volume:34 Page:351-353
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Seltzer M.S.,Clauer A.H.,Wilcox B.A.

Publisher

Elsevier BV

Subject

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

Reference9 articles.

1. Grain boundary reactions during deformation;Poteat,1968

2. Mechanical properties of oxide fuels;Wolfe;Westinghouse (USA) Report WAPD-TM-587,1967

3. Compressive creep characteristics of ceramic oxide nuclear fuels: part I Uranium dioxide;Bohaboy,1968

4. P. E. Bohaboy and R. R. Asamoto, General Electric Company, Advanced Products Division, Sunnyvale, California, private communication.

5. Creep deformation of stoichiometric uranium dioxide

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1. Versatility of dislocation motions in polycrystalline UO2 deformed at 1550 °C investigated by TEM;Scripta Materialia;2024-04

2. Diffusional Creep Model in Uo2 Informed by Lower-Length Scale Simulations;2024

3. Viscoplastic behavior of a porous polycrystal with similar pore and grain sizes: Application to nuclear MOX fuel materials;International Journal of Solids and Structures;2022-02

4. The effect of oxygen partial pressure on dislocation creep in polycrystalline uranium dioxide;Journal of the European Ceramic Society;2021-03

5. Creep in Ceramics;Creep in Ceramics;2017

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