Carbides for Future Fission Environments (CAFFE)

用于未来裂变环境的碳化物（CAFFE）

• 批准号: EP/M018768/1
• 负责人: Ian Farnan
• 金额: $ 55.78万
• 依托单位: University of Cambridge
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2015
• 资助国家: 英国
• 起止时间: 2015 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FM018768%2F1
• 关键词: Carbides; Future; Fission; Environments; CAFFE

Summary (4000 characters)This project will bring together eight investigators from world leading research and nuclear research universities together with three post-doctoral fellows and three PhD students to investigate zirconium carbide ceramic materials for their potential application in advanced nuclear reactor systems. These materials will be required to operate at high temperatures and suffer large numbers of atomic displacements due to radiation damage and yet will be required to resist corrosion and provide longer lifetimes than current materials. Following recommendations from international reports on the development of new materials for advanced fission reactors, the most modern techniques in materials modelling and characterisation and testing will be brought to bear on these new materials. Phase diagrams will be calculated for new proposed layered zirconium carbide ceramics to guide the preparation of new phases. These new phases and a few already known phases will be characterised on multiple scales with 13C nuclear magnetic resonance, transmission electron and synchrotron diffraction and lab-based x-ray tomography both before and after their irradiation and corrosion testing at the National Nuclear Users Facility/Dalton Cumbria Facility. The researchers will collaborate with leading players in the nuclear materials industry to evaluate the neutronics and manufacturability of these new materials to assess their potential to be carried forward to later stages of development. An international meeting will be hosted at the end of the programme to highlight progress made in the development of these materials to both to the wider industry and to international academic groups to increase the profile of the UK Nuclear Materials community in Generation IV and Generation III+ nuclear research.

该项目将汇集来自世界领先的研究和核研究大学的8名研究人员，以及3名博士后研究员和3名博士生，研究碳化锆陶瓷材料在先进核反应堆系统中的潜在应用。这些材料将需要在高温下工作，并且由于辐射损伤而遭受大量的原子位移，并且还需要耐腐蚀并提供比当前材料更长的寿命。根据国际报告中关于先进裂变反应堆新材料开发的建议，材料建模、表征和测试方面的最现代技术将用于这些新材料。将计算新提出的层状碳化锆陶瓷的相图，以指导新相的制备。这些新的阶段和一些已知的阶段将在多个尺度上的13 C核磁共振，透射电子和同步辐射衍射和实验室为基础的X射线断层扫描之前和之后，在国家核用户设施/道尔顿坎布里亚设施的辐照和腐蚀测试。研究人员将与核材料行业的主要参与者合作，评估这些新材料的中子学和可制造性，以评估它们在后期开发阶段的潜力。该计划结束时将举办一次国际会议，以突出这些材料的开发进展，以更广泛的行业和国际学术团体，以提高英国核材料社区在第四代和第三代+核研究中的形象。

项目成果

Mechanism and Kinetics of Oxidation of ZrN Ceramics

• DOI: 10.1111/jace.13575
• 发表时间: 2015-07-01
• 期刊: JOURNAL OF THE AMERICAN CERAMIC SOCIETY
• 影响因子: 3.9
• 作者: Harrison, Robert W.;Lee, William Edward
• 通讯作者: Lee, William Edward

Point defect formation in M2AlC (M = Zr,Cr) MAX phases and their tendency to disorder and amorphize

M2AlC (M = Zr,Cr) MAX 相中点缺陷的形成及其无序和非晶化的趋势

• DOI: 10.17863/cam.12209
• 发表时间: 2017
• 作者: Bristowe P

Effect of magnetism and temperature on the stability of (Cr-x, V1-x)(2)AlC phases

磁性和温度对(Cr-x, V1-x)(2)AlC相稳定性的影响

• DOI: 10.17863/cam.35738
• 发表时间: 2018
• 作者: Grossi J

Synthesis and DFT investigation of new bismuth-containing MAX phases.

• DOI: 10.1038/srep18829
• 发表时间: 2016-01-07
• 期刊: Scientific reports
• 影响因子: 4.6
• 作者: Horlait D;Middleburgh SC;Chroneos A;Lee WE
• 通讯作者: Lee WE