核反应堆堆芯材料的应变局部化与断裂

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
M. Griffiths
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引用次数: 2

摘要

核反应堆堆芯材料中棱柱形位错环的产生阻碍了位错的运动,导致了位错的硬化。屈服通常是通过与称为通道的滑动位错相互作用而局部清除环路而发生的。清除的通道代表一种较软的材料,其中大部分后续变形都是局部化的。通道通常与假设的位错堆积和反应堆组件的晶间开裂有关,尽管通道本身并不像人们所期望的堆积那样放大应力。通道通常在外观上与双胞胎相似,导致双胞胎有时可能被错误地识别为通道。无论是孪生体还是位错通道,它们都是块状剪切,都不会产生与单一平面上的堆积相同的应力条件。在高剂量下,当产生空腔(低温下氦稳定的气泡或高温下的空洞)时,材料的延展性会降低,因为材料已经处于微观颈缩的等效高级阶段。he稳定空腔优先形成于晶界和析出相或非共格孪晶/ε-马氏体界面。较高的空腔平面密度,加上界面处的不相容,导致优先破坏称为He脆化。应变局部化和颗粒间或颗粒内的破坏取决于许多因素,这些因素最终都是微观结构的。描述和讨论了与堆芯材料有关的机理。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Strain Localisation and Fracture of Nuclear Reactor Core Materials
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/ε-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.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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