Atomistic Scale Study of Radiation Effects in ABO3 Perovskites

核电的发展正处于一个重要的关头，有两种相互竞争但在许多方面相互补充的技术：聚变和裂变。然而，尽管核方法不同，但工程挑战是相同的，即在结构受到高水平辐射损害和残留核产品的情况下，需要去除产生的热量。特别是，辐射损伤效应和气泡形成是聚变堆和第四代裂变反应堆发展的难题。例如，在GenIV裂变核中，Xe和Kr气体来自裂变核，即Pu和U，而在聚变核中，他是在D-T等离子体中形成的。本方案以可调谐钙钛矿为模型材料，重点研究了以下问题：1.非放射性离子束诱导可调谐陶瓷中晶态向非晶态转变的机制。主要是裂变反应堆材料，如氧化物燃料和消耗臭氧层物质材料中微结构陷阱处的气泡成核，但可由聚变等离子体氦注入形成气泡成核，以及聚变堆芯材料中使用的材料的损伤，如ITER和DEMO中被建议为磁包容的YBCO超导体。研究将采用实验和模拟技术相结合的整体方法。实验研究将利用原位和整体照射，主要结合先进的电子显微镜和原子探针断层扫描。补充模拟方案将以辐照材料为基础，但重点放在恢复机制、气泡演化和对当前模型的验证上。研究成果将用于开发用作两种燃料的新材料，例如惰性基质，或用作热核实验堆/DEMO中的磁遏制装置。这项研究的信息也可用于其他非标准反应堆技术，如行波设计。所得到的信息也将有助于设计未来的钚/铀废物形式，特别是进入能够容忍辐射损伤和气泡形成的新阶段。

SummaryThe development of nuclear power is at an important juncture, with two competing but in many ways complementary technologies: fusion and fission. However, while the nuclear methodology is different the engineering challenge is the same, that is, the need to remove the generated heat while structures are subject to high levels of radiation damage and residual nuclear products. In particular, radiation damage effects and gas bubble formation are problematic issues for the development of both fusion and GenIV fission reactors. For example in a GenIV fission core, the Xe and Kr gas comes from fission of the fissile nuclei, that is, Pu and U, while in a fusion core He is formed within the D-T plasma. This proposal aims to address these issues using tunable perovskites, as model materials, and focusing on the following issues:1. Crystalline to amorphous transformation mechanisms in tunable ceramics instigated using non-radioactive ion beams.2. Bubble nucleation at micro-structural traps in predominantly fission reactor materials, e.g. oxide based fuels, and ODS materials, but which can be formed by He implantation from fusion plasma He nucleation, and damage in materials for use in fusion cores, such as YBCO superconductors suggested as magnetic containment in for example, ITER and DEMO.The research will be undertaken using the approach of experimental and simulation techniques combined holistically. The experimental study will utilise in-situ and bulk irradiation, primarily in combination with advanced electron microscopy and atom probe tomography. The complementary simulation programme will be based on irradiated materials, but focusing on recovery mechanisms, bubble evolution, and validation of current models. The outcomes of the research will be used in the development of new materials for use as both fuels, for example Inert Matrix, or as magnetic containment devices in ITER/DEMO. The information from this research can also be utilised in other non-standard reactor technologies such as the travelling wave designs.The information derived will also help the design of future waste forms for Pu/U, specifically into new phases capable of tolerating the effects of radiation damage, and He bubble formation.