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Ion irradiations of fusion reactor materials

聚变反应堆材料的离子辐照

基本信息

批准号：
EP/F004451/1
负责人：
Steven Roberts
金额：
$ 6.22万
依托单位：
University of Oxford
依托单位国家：
英国
项目类别：
Research Grant
财政年份：
2007
资助国家：
英国
起止时间：
2007 至无数据
项目状态：
已结题

来源：
https://gtr.ukri.org/projects?ref=EP%2FF004451%2F1
关键词：
Ion irradiations fusion reactor materials

项目摘要

To optimise materials for operation in a fusion environment, we need to develop a mechanistic understanding of their mechanical properties and of the changes in mechanical properties induced by irradiation. An ongoing project at Oxford has concentrated on developing an understanding of the mechanical properties of unirradiated materials and on studies of the evolution of radiation damage in thin electron microscope specimens by 50-100keV heavy-ion irradiation. There are difficulties with using thinned specimens, in that defects can relatively easily escape from the free surfaces of the specimens; the damage observed may not be typical of that introduced by cascades initiated by neutron irradiation deep within a material. Hence we now need to study materials irradiated with MeV heavy ions in the bulk.The feasibility of using the Surrey University facility for such studies has been demonstrated in a trial implantation of FeCr alloys. Our first microscopy experiments have shown a high density of resolvable dislocation loops, qualitatively similar to the microstructures seen in neutron-irradiated FeCr alloys. We now need to carry out a set of systematic irradiation experiments, where we will irradiate a wider range of materials, and study the resultant radiation damage and its effects on mechanical properties. We will include both TEM and microbeam specimens of Fe, FeCr (up to 12% Cr), RAFM and ODS steels. The experiments will also be extended to materials pre-implanted with He+ immediately before Fe+ irradiation, so as to simulate the effects of transmutation gases. Transmission electron microscopy will be used to study irradiation damage and post-damage and deformation dislocation structures in each of the materials, including specimens cut from the microbeams before and after deformation. The aim will be a complete microstructural characterisation of dislocations, dislocation loops and voids using a full range of TEM techniques, including both standard diffraction-contrast and high-resolution methods and novel techniques developed by M.L. Jenkins and co-workers. Advanced analytical techniques will be used to study local chemistry, for example at the interfaces of ODS particles. Micro-beams will be used to study the elastic, plastic and fracture behaviour of irradiated materials. We will study the bulk properties of the materials, by cutting specimens within single grains. Grain boundary segregation and embrittlement will be studied as a function of grain boundary crystallography, local chemistry and radiation damage. Slip transmission through boundaries will be studied by loading of microbeams containing a boundary and an indentation as a local dislocation source. Fracture strength of boundaries will be studied by notching of boundaries within bend specimens.

为了优化材料在聚变环境中的操作，我们需要对它们的机械性能和辐照引起的机械性能变化进行机械理解。牛津大学的一个正在进行的项目集中于发展对未辐照材料的机械性能的理解，并研究50- 100 keV重离子辐照下薄电子显微镜样品中辐射损伤的演变。有困难与使用薄的标本，在缺陷可以相对容易地逃脱从自由表面的标本，观察到的损害可能不是典型的级联引起的中子辐照材料深处。因此，我们现在需要研究材料辐照MeV重离子在bulk.The使用萨里大学的设施进行此类研究的可行性已被证明在试验植入的FeCr合金。我们的第一个显微镜实验显示了高密度的可分辨位错环，定性类似于中子辐照的FeCr合金中看到的微观结构。我们现在需要进行一系列系统的辐照实验，在这些实验中，我们将对更广泛的材料进行辐照，并研究由此产生的辐射损伤及其对机械性能的影响。我们将包括Fe，FeCr（高达12%Cr），RAFM和ODS钢的TEM和微束试样。实验还将扩展到在Fe+辐照之前立即预注入He+的材料，以模拟嬗变气体的影响。透射电子显微镜将用于研究辐照损伤和损伤后和变形位错结构中的每一种材料，包括从变形前后的微梁切下的标本。目标是使用全方位的TEM技术，包括标准衍射对比和高分辨率方法以及M. L. Jenkins和同事们先进的分析技术将用于研究当地的化学性质，例如在消耗臭氧层物质颗粒的界面处。微束将用于研究受辐照材料的弹性、塑性和断裂行为。我们将通过在单个晶粒内切割样品来研究材料的整体性质。晶界偏析和脆化将作为晶界晶体学，局部化学和辐射损伤的功能进行研究。通过加载包含边界和压痕作为局部位错源的微梁，将研究通过边界的滑移传输。将通过在弯曲试样内对边界开槽来研究边界的断裂强度。

项目成果

期刊论文数量（10）

专著数量（0）

科研奖励数量（0）

会议论文数量（0）

专利数量（0）

Effects of Ion Irradiation on the Microstructure of an ODS/Fe12Cr Alloy

离子辐照对 ODS/Fe12Cr 合金显微组织的影响

DOI：
发表时间：
2009
期刊：
影响因子：
0
作者：
De Castro, V
通讯作者：
De Castro, V

Effect of dislocation density on improved radiation hardening resistance of nano-structured tungsten-rhenium

DOI：
10.1016/j.msea.2014.06.013
发表时间：
2014-08-12
期刊：
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
影响因子：
6.4
作者：
Armstrong, David E. J.;Britton, T. B.
通讯作者：
Britton, T. B.

Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium