Characterization of the atomic scale structure of yttria-based particles in oxide dispersion strengthened steels

氧化物弥散强化钢中氧化钇基颗粒的原子尺度结构表征

• 批准号: EP/I012400/1
• 负责人: Chris Grovenor
• 金额: $ 18.74万
• 依托单位: University of Oxford
• 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%2FI012400%2F1
• 关键词: Characterization; atomic; scale; structure; yttria

It has been predicted that by 2012 the UK's electricity generating capacity will no longer meet demand. Reliable large sources of electrical power will be vital for social stability and to maintain a manufacturing industry base. Nuclear fusion and advanced fission power plants have been proposed, with switch-on dates in the range 2025 (advanced fission) to 2050 (fusion). These have the potential for large-scale, clean, CO2-free power generation for generations. However, the structural materials from which the power plants' core components will be built must have high strength and toughness at high temperatures, and retain good properties for decades under severe radiation damage. Many elements ordinarily used in strong alloys cannot be used because their transmutation products are highly radioactive for thousands of years, so we must design new strong alloys using a very restricted range of elements. Second, helium is produced in most reactions, and adds to the embrittling effects of the radiation damage.Oxide Dispersion Strengthened alloys are a relatively new class of steels that are expected to play an important role as structural materials in future generations of nuclear reactors (the so-called GenIV reactors). These alloys offer much improved performance than more conventional structural steels at the temperatures above 600 C that will be experienced in these new reactor designs. However, there are a number of issues that are very poorly understood in these alloys.- When, and at what rate, the dispersions are generated during thermo-mechanical processing- What the interface chemistry and atomic structure is- What effect this interface has on absorbing the products of irradiation- How best to integrate modelling to help understand both fabrication mechanisms and radiation resistance.This project is to combine fabrication expertise in the Indira Ghandhi Centre for Atomic Research in Kalpakkam, atomic scale characterisation expertise in Oxford and IGCAR and at the Diamond facility at the Rutherford Appleton Laboaratory, and the modelling expertise at Loughborough, to undertake a programme of work to explore the fundamental metallurgy of ODS materials with the aim of designing new alloys with improved properties.

据预测，到2012年，英国的发电能力将不再满足需求。可靠的大型电力来源对于社会稳定和维持制造业基础至关重要。已经提出了核融合和晚期裂变发电厂，其开关日期在2025年（晚期裂变）至2050年（融合）。这些可能会产生几代人的大规模，干净，无二氧化碳的发电。但是，将在高温下建造发电厂核心组件的结构材料必须具有高强度和韧性，并且在严重的辐射损害下保留了数十年的良好特性。由于它们的透射产品在数千年的时间内具有很高的放射性，因此无法使用许多用于强合金中的元素，因此我们必须使用非常有限的元素设计新的强合金。其次，氦是在大多数反应中产生的，并增加了辐射损伤的影响效应。氧化物分散剂增强的合金是一类相对较新的钢，预计将在后代的核反应堆（所谓的Geniv Reactors）中作为结构材料发挥重要作用。这些合金比在这些新反应堆设计中会经历的600 C高于600 C的温度中，提供的性能要高得多。但是，在这些合金中有很多问题。-何时以及以何种速度的速度产生的分散物是在热机械处理过程中产生的 - 界面化学和原子结构是什么？该界面对吸收辐射的产物具有什么影响 - 对辐射的产物产生了什么影响 - 对如何最好地集成了制造机制的构图，以帮助组合构建机制，以组合构造的构造，包括组合组合的组合。在牛津和Igcar的Kalpakkam，原子量表的特征专业知识以及Rutherford Appleton Laboararation的钻石设施以及Loughborough的建模专业知识，以进行一项工作计划，以探索ODS材料的基本金属材料，以设计新的同类物业的目的是设计新的同类物业的目标。

项目成果

Effect of Ti and Cr on dispersion, structure and composition of oxide nano-particles in model ODS alloys

• DOI: 10.1016/j.actamat.2015.06.032
• 发表时间: 2015-09
• 期刊: Acta Materialia
• 影响因子: 9.4
• 作者: A. London;S. Santra;S. Amirthapandian;B. Panigrahi;R. M. Sarguna;S. Balaji;R. Vijay;C. S. Sundar-C.-S.-Sun

Helium bubbles in bcc Fe and their interactions with irradiation

• DOI: 10.1016/j.jnucmat.2014.10.027
• 发表时间: 2015-07
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: Xiao Gai;T. Lazauskas;Roger Smith;S. Kenny

Comparison of atom probe tomography and transmission electron microscopy analysis of oxide dispersion strengthened steels

• DOI: 10.1088/1742-6596/522/1/012028
• 发表时间: 2014-01-01
• 期刊: ELECTRON MICROSCOPY AND ANALYSIS GROUP CONFERENCE 2013 (EMAG2013)
• 作者: London, A. J.;Lozano-Perez, S.;Grovenor, C. R. M.
• 通讯作者: Grovenor, C. R. M.

Simulating radiation damage in a bcc Fe system with embedded yttria nanoparticles

• DOI: 10.1016/j.jnucmat.2013.02.016
• 发表时间: 2013-06
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: T. Lazauskas;S. Kenny;Roger Smith;G. Nagra;Manan Dholakia;M. C. Valsakumar

Glancing angle XRD analysis of particle stability under self-ion irradiation in oxide dispersion strengthened alloys

• DOI: 10.1016/j.scriptamat.2015.07.037
• 发表时间: 2016-01-01
• 期刊: SCRIPTA MATERIALIA
• 影响因子: 6
• 作者: London, A. J.;Panigrahi, B. K.;Grovenor, C. R. M.
• 通讯作者: Grovenor, C. R. M.