Strain Localisation and Fracture of Nuclear Reactor Core Materials

被引:6
作者
Griffiths, Malcolm [1 ,2 ,3 ]
机构
[1] Queens Univ, Dept Mech & Mat Engn, Kingston, ON K7L3N6, Canada
[2] Carleton Univ, Dept Mech & Aerosp Engn, Ottawa, ON K1S5B6, Canada
[3] ANT Int, S-44850 Tollered, Sweden
来源
JOURNAL OF NUCLEAR ENGINEERING | 2023年 / 4卷 / 02期
关键词
Irradiation; nuclear reactors; strain localization; dislocation; channeling; twin; martensite; helium; bubbles; cavities; embrittlement; swelling; creep; microstructure; texture; Zr-alloys; austenitic stainless steel; Ni-alloys; AUSTENITIC STAINLESS-STEELS; STRESS-CORROSION CRACKING; IRRADIATION CREEP; MICROSTRUCTURAL CHARACTERIZATION; DEFORMATION LOCALIZATION; NEUTRON-IRRADIATION; INCONEL X-750; DISLOCATION; BEHAVIOR; ALLOYS;
D O I
10.3390/jne4020026
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The production of prismatic dislocation loops in nuclear reactor core materials results in hardening because the loops impede dislocation motion. Yielding often occurs by a localised clearing of the loops through interactions with gliding dislocations called channeling. The cleared channels represent a softer material within which most of the subsequent deformation is localized. Channeling is often associated with hypothetical dislocation pileup and intergranular cracking in reactor components although the channels themselves do not amplify stress as one would expect from a pileup. The channels are often similar in appearance to twins leading to the possibility that twins are sometimes mistakenly identified as channels. Neither twins nor dislocation channels, which are bulk shears, produce the same stress conditions as a pileup on a single plane. At high doses, when cavities are produced (either He-stabilised bubbles at low temperatures or voids at high temperatures), there can be reduced ductility because the material is already in an equivalent advanced stage of microscopic necking. He-stabilised cavities form preferentially on grain boundaries and at precipitate or incoherent twin/epsilon-martensite interfaces. The higher planar density of the cavities, coupled with the incompatibility at the interface, results in a preferential failure known as He embrittlement. Strain localisation and inter- or intragranular failure are dependent on many factors that are ultimately microstructural in nature. The mechanisms are described and discussed in relation to reactor core materials.
引用
收藏
页码:338 / 374
页数:37
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