Atomistic Scale Study of Radiation Effects in ABO3 Perovskites

核能的发展正处于一个重要的关口，有两种相互竞争但在许多方面互补的技术：聚变和裂变。然而，虽然核方法不同，但工程挑战是相同的，即需要在结构受到高水平辐射损害和残留核产物的同时消除产生的热量。特别是，辐射损伤效应和气泡形成是聚变和GenIV裂变反应堆发展的问题。例如，在第四代裂变堆芯中，氦和氪气体来自裂变核的裂变，即钚和铀，而在聚变堆芯中，氦在D-T等离子体中形成。本提案旨在使用可调钙钛矿作为模型材料来解决这些问题，并关注以下问题：1。非放射性离子束激发可调陶瓷晶体向非晶转变的机制.在主要裂变反应堆材料（例如基于氧化物的燃料和ODS材料）中的微结构阱处的气泡成核，但是其可以通过来自聚变等离子体He成核的He注入形成，以及在用于聚变芯的材料（例如在例如，将采用实验和模拟技术相结合的方法进行研究。实验研究将利用原位和批量照射，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，但侧重于恢复机制、气泡演变和验证现有模型。研究成果将用于开发既可用作燃料的新材料，例如惰性基质，也可用作ITER/DEMO中的磁性密封装置。这项研究的信息也可以用于其他非标准反应堆技术，如行波设计，所获得的信息也将有助于设计未来的钚/铀废物形式，特别是能够承受辐射损伤和He气泡形成的影响的新阶段。

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.