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Linking Microstructure to Neutron Irradiation Defects in Advanced Manufacture of Steels

将微观结构与先进钢制造中的中子辐照缺陷联系起来

基本信息

批准号：
EP/P005101/1
负责人：
Mark Wenman
金额：
$ 84.74万
依托单位：
Imperial College London
依托单位国家：
英国
项目类别：
Research Grant
财政年份：
2016
资助国家：
英国
起止时间：
2016 至无数据
项目状态：
已结题

来源：
https://gtr.ukri.org/projects?ref=EP%2FP005101%2F1
关键词：
Linking Microstructure Neutron Irradiation Defects

项目摘要

The UK plans to build a new fleet of nuclear power plants starting with two units at Hinkley Point in Somerset. The UK government has also recently announced in the autumn 2015 statement that £250M will be set aside for in innovative nuclear technologies. More specifically it has stated that the UK will invest in small modular reactor designs. The large reactors and many small modular reactor designs are based around a reactor type called a pressurised water reactor. These reactor designs have a steel reactor pressure vessel to enclose the nuclear fuel and act as a key barrier to the release of radiotoxic materials to the environment. The integrity of the vessels is paramount to the safety and continued operation of the reactor. Unfortunately, neutron irradiation from the nuclear fuel damages the steels over their 40-60 year design life. Understanding the role of neutron damage to these steels is therefore key to continued operation beyond the design life. This programme of work will study commonly used reactor pressure vessel forging grade steels (A508 class 3), under neutron irradiation damage, at the OPAL test reactor, at Lucas Heights in Australia. The steels will be manufactured by processes not commonly used in nuclear reactors i.e. hot isostatic pressing (HIP) of powdered material and then welded using electron beams (EB). These new manufacturing processes could potentially be used to manufacture parts for the reactor pressure vessels of future small reactor designs. As yet there is no information on how changing the manufacturing routes from arc welding of forged material to EB welding of HIPed material will change the neutron irradiation response of the material. In this case the chemistry of the material remains unchanged so the key variable is the so-called "microstructure" of the material.It is planned to irradiate samples, at the OPAL reactor, for up to 1 year, to achieve doses of neutron embrittlement equivalent to 40-60 years reactor operation. The irradiated material will then be mechanically tested, in hot cells, at the Australian Nuclear Science and Technology Organisation before material is shipped to the new Materials Research Faclility at UKAEA Culham site in the UK. Here, it will be prepared for state-of-the-art characterisation, by atom probe tomography on the new LEAP 5000 atom probe recently installed at Oxford University, Chemi-STEM transmission electron microscopy at Manchester University, together with atomic scale models developed at Imperial College London and Manchester University. The project will also have management and input from the National Nuclear Laboratory and Rolls-Royce and international links to the University of New South Wales, University of California Santa Barbara and Oak Ridge National Laboratory.The overall output from this work will be much improved mechanistic understanding and models of how neutron irradiation effects steels manufactured by HIP and EB welding, lead to a new generation of engineers in the UK who can perform work on irradiated materials and help direct the use of such technologies for the building of future small reactor designs. It will also be a crucial driver in the effort to rebuild the physical and knowledge based infrastructure, for dealing with neutron irradiated steels, that has been missing for a generation in the UK.

英国计划从萨默塞特欣克利角的两座核电站开始建设一批新的核电站。英国政府最近还在 2015 年秋季声明中宣布，将拨出 2.5 亿英镑用于创新核技术。更具体地说，它表示英国将投资小型模块化反应堆设计。大型反应堆和许多小型模块化反应堆设计都是基于称为压水堆的反应堆类型。这些反应堆设计有一个钢制反应堆压力容器，用于封闭核燃料，并充当放射性毒性材料释放到环境中的关键屏障。容器的完整性对于反应堆的安全和持续运行至关重要。不幸的是，核燃料的中子辐射会在钢材 40-60 年的设计寿命期间对其造成损坏。因此，了解中子损伤对这些钢的作用是在设计寿命之外继续运行的关键。该工作计划将在澳大利亚卢卡斯高地的 OPAL 测试反应堆中研究中子辐照损伤下常用的反应堆压力容器锻造级钢（A508 3 级）。这些钢材将采用核反应堆中不常用的工艺制造，即粉末材料的热等静压（HIP），然后使用电子束（EB）焊接。这些新的制造工艺有可能用于制造未来小型反应堆设计的反应堆压力容器的零件。迄今为止，还没有关于从锻造材料的电弧焊到 HIPed 材料的电子束焊接的制造路线的改变将如何改变材料的中子辐照响应的信息。在这种情况下，材料的化学性质保持不变，因此关键变量是材料的所谓“微观结构”。计划在 OPAL 反应堆中辐照样品长达 1 年，以达到相当于反应堆运行 40-60 年的中子脆化剂量。然后，经过辐照的材料将在澳大利亚核科学技术组织的热室中进行机械测试，然后将材料运送到英国 UKAEA 卡勒姆基地的新材料研究设施。在这里，它将通过牛津大学最近安装的新型 LEAP 5000 原子探针上的原子探针断层扫描、曼彻斯特大学的 Chemi-STEM 透射电子显微镜以及伦敦帝国理工学院和曼彻斯特大学开发的原子尺度模型，为最先进的表征做好准备。该项目还将获得国家核实验室和劳斯莱斯的管理和投入，以及与新南威尔士大学、加州大学圣巴巴拉分校和橡树岭国家实验室的国际联系。这项工作的总体成果将大大改善对中子辐照如何影响 HIP 和 EB 焊接制造的钢材的机械理解和模型，从而培养英国新一代工程师，他们可以对辐照材料进行研究，并帮助指导此类技术的使用用于建造未来的小型反应堆设计。它还将成为重建物理和知识基础设施的关键驱动力，以处理中子辐照钢材，而英国已经缺失了一代人的时间。

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）

Micromechanical testing of unirradiated and helium ion irradiated SA508 reactor pressure vessel steels: Nanoindentation vs in-situ microtensile testing

DOI：
10.1016/j.msea.2020.139942
发表时间：
2020-10-07
期刊：
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
影响因子：
6.4
作者：
Gasparrini, C.;Xu, A.;Wenman, M. R.
通讯作者：
Wenman, M. R.

Density functional theory study of the magnetic moment of solute Mn in bcc Fe