Irradiation Effects on Flow Localisation in Zirconium Alloys

辐照对锆合金流动局域化的影响

• 批准号: EP/I012346/1
• 负责人: Michael Preuss
• 金额: $ 40.63万
• 依托单位: University of Manchester
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2011
• 资助国家: 英国
• 起止时间: 2011 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FI012346%2F1
• 关键词: Irradiation; Effects; Flow; Localisation; Zirconium

This project focuses on energy and more specifically on nuclear fission. Core material such as fuel assemblies are exposed to irradiation from the moment a nuclear reactor is switched on. The bombardment of material with neutrons creates collision cascades that immediately produce point defects and dislocations in the material. This results in very significant changes of the material properties compared to non-irradiated material.Nuclear fuel for light water reactors is contained by so-called cladding tubes, which are made from zirconium alloys because of their excellent corrosion resistance, sufficient mechanical properties and their low neutron absorption coefficient. Nuclear fuel is enriched initially with 5% 235U. However, the fuel cannot be fully burned due to the uncertainty of clad material degradation and dimensional instability of fuel assemblies. The safe operation of nuclear fuel assemblies requires a complete understanding of the mechanical properties of irradiated material. For instance, when strained plastically, irradiated materials display severe flow localisation and in the case of zirconium also a change from prismatic to basal slip. Consequently, we need to develop a detailed understanding of the mechanisms leading to these phenomena and how they are affected by material chemistry and the microstructure evolution during irradiation.During the 1960s and 70s many countries including the UK had test reactors that allowed scientists to undertake research on irradiated material. However, most of these test reactors are gone now and it is unlikely that the UK or other countries will build many new test reactors. For this reason, governments have invested in proton/ion accelerators to simulate neutron irradiation. The advantage of such facilities is that they are by many order of magnitudes cheaper to run than a test reactor. However, our understanding of how well neutron induced damage is related to proton/ion induced damage is limited. Since Zr alloys are relatively mildly active when irradiated by neutrons, they represent also an ideal material to calibrate proton/ion against neutron irradiation.The research will be undertaken in a collaborative effort between the UK and India with the aim to train Indian researchers to undertake advanced electron back scatter diffraction (EBSD) and synchrotron x-ray diffraction experiments. Neutron irradiated material will be provided by the TIFR/BARC facility, Mumbai, India while ion irradiation will be carried out at the new Dalton Cumbria Facility in the UK.

该项目的重点是能源，更具体地说是核裂变。从核反应堆启动的那一刻起，燃料组件等核心材料就会受到辐射。中子轰击材料会产生碰撞级联，立即在材料中产生点缺陷和位错。与未辐照材料相比，这导致材料性能发生非常显着的变化。轻水反应堆的核燃料包含在所谓的包壳管中，包壳管由锆合金制成，因为它们具有优异的耐腐蚀性、足够的机械性能和中子吸收系数低。核燃料最初浓缩为 5% 235U。然而，由于包层材料降解的不确定性和燃料组件的尺寸不稳定性，燃料无法完全燃烧。核燃料组件的安全运行需要完全了解辐照材料的机械性能。例如，当塑性应变时，辐照材料表现出严重的流动局部化，并且在锆的情况下，还会出现从棱柱滑移到基底滑移的变化。因此，我们需要详细了解导致这些现象的机制，以及它们如何受到材料化学和辐照过程中微观结构演变的影响。在 20 世纪 60 年代和 70 年代，包括英国在内的许多国家都拥有允许科学家进行研究的测试反应堆在辐照材料上。然而，这些试验堆大部分已经消失，英国或其他国家不太可能建造许多新的试验堆。因此，各国政府投资了质子/离子加速器来模拟中子辐照。此类设施的优点是其运行成本比试验反应堆便宜许多数量级。然而，我们对中子引起的损伤与质子/离子引起的损伤之间的关系的理解是有限的。由于Zr合金在受到中子辐照时活性相对温和，因此它们也是校准质子/离子对抗中子辐照的理想材料。这项研究将由英国和印度合作进行，旨在培训印度研究人员进行先进的电子背散射衍射 (EBSD) 和同步加速器 X 射线衍射实验。中子辐照材料将由印度孟买的 TIFR/BARC 设施提供，而离子辐照将在英国新的道尔顿坎布里亚设施进行。

项目成果

Microscopic strain localisation in Ti-6Al-4V during uniaxial tensile loading

• DOI: 10.1016/j.msea.2016.10.099
• 发表时间: 2017-01-05
• 期刊: MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
• 影响因子: 6.4
• 作者: Lunt, D.;da Fonseca, J. Quinta;Preuss, M.
• 通讯作者: Preuss, M.

Influence of Sn on Deformation Mechanisms During Room Temperature Compression of Binary Zr-Sn Alloys

Sn对Zr-Sn二元合金室温压缩变形机制的影响

• 发表时间: 2015
• 作者: Mani Krishna, K.V.

Effects of alloying elements on the formation of < c >-component loops in Zr alloy Excel under heavy ion irradiation

重离子辐照下合金元素对Zr合金Excel中<c>组分环形成的影响

• DOI: 10.1557/jmr.2015.89
• 发表时间: 2015
• 期刊: Journal of Materials Research
• 影响因子: 2.7
• 作者: Idrees Y

Microstructure and texture evolution during thermomechanical processing of ß-quenched Zr

淬火Zr热机械加工过程中的显微组织和织构演变

• DOI: 10.1016/j.actamat.2014.12.033
• 发表时间: 2015
• 期刊: Acta Materialia
• 影响因子: 9.4
• 作者: Leo Prakash D

The effect of loading direction and Sn alloying on the deformation modes of Zr: An in-situ neutron diffraction study

• DOI: 10.1016/j.msea.2015.10.047
• 发表时间: 2016-01
• 期刊: Materials Science and Engineering A-structural Materials Properties Microstructure and Processing
• 影响因子: 6.4
• 作者: K. Krishna;D. Prakash;G. Timár;Arnas Fitzner;D. Srivastava;N. Saibaba;J. Fonseca;G. K. Dey;M. Preuss