Isotope labeling for quantitative determination of defect sink strength and fundamentals studies on defect-sink interactions

用于定量测定缺陷汇强度的同位素标记以及缺陷汇相互作用的基础研究

• 批准号: 1708788
• 负责人: Lin Shao
• 金额: $ 38.5万
• 依托单位: Texas A&M Engineering Experiment Station
• 依托单位国家: 美国
• 项目类别: Standard Grant
• 财政年份: 2017
• 资助国家: 美国
• 起止时间: 2017-07-01 至 2020-06-30
• 项目状态: 已结题
• 来源: https://www.nsf.gov/awardsearch/showAward?AWD_ID=1708788&HistoricalAwards=false
• 关键词: Isotope; labeling; quantitative; determination; defect

Nontechnical AbstractNuclear power is one solution to meet the ever-increasing demand for energy. One key issue in the so called "nuclear renaissance" is materials development towards longer life time under harsh environments. In order to withstand neutron damage at high temperatures, various nanostructured materials have been developed by introducing defect sinks to absorb/remove defects. However, quantitative determination of defect sink strength is still a technological bottleneck. This project uses an isotope labeling technique to quantitatively measure the sink strength in ion irradiated stainless steels as a key approach for a full scope investigation on defect-sink interactions. Such capability is critical to develop radiation tolerant materials. Even for the same type of defect sinks, fine tuning of their microstructures to maximize sink strength requires knowledge of one-to-one correlation between structures and sink strength. The study will contribute to the general understanding of defects in metals. The project offers students unique opportunities to combine training and research in nuclear engineering, nanomaterials, atomic scale characterization and atomic scale modeling, for solving issues of real-world importance. Technical AbstractFor Fe based stainless steels of nature Fe abundance, implantation of 57Fe isotope atoms will introduce 57Fe interstitials. Upon annealing, the amount of 57Fe enrichments at defect sinks directly reflects the sink strength for defect trapping. Hence the defect sink strength under different irradiation/annealing/stress conditions can be systematically studied. Three-dimensional atom probe tomography (APT) will be used to map 57Fe isotope distributions. APT is coupled with transmission electron microscopy (TEM) and 3-D TEM tomography to establish one-to-one correlation between defect sink structure and sink strength. The project will study two defect sink types: (1) grain boundaries in grain-engineered stainless steels in order to understand effects of boundary misorientation angles on sink strength and (2) oxide particles in oxide-dispersion-strengthened alloys (ODS) in order to understand the effects of oxide-matrix interfaces on sink strength. The project further integrates molecular dynamics simulations to shed light onto fundamentals. The defect sink strength will be used as inputs in kinetic Monte Carlo simulations for obtaining structural evolutions which can be linked to and compared with experimental observations. In conjunction with materials synthesis, modeling, and atomic scale characterization, the project will obtain the fundamental understanding needed to maximize radiation tolerance of reactor core components. The project offers students unique opportunities to combine training and research in nuclear engineering, nanomaterials, atomic scale characterization and atomic scale modeling, for solving issues of real-world importance.

核能是满足日益增长的能源需求的一种解决方案。所谓的“核复兴”的一个关键问题是在恶劣环境下开发更长寿命的材料。为了承受高温下的中子损伤，已经通过引入缺陷汇以吸收/去除缺陷来开发了各种纳米结构材料。然而，缺陷下沉强度的定量测定仍然是一个技术瓶颈。 本计画利用同位素标记技术，以定量量测经离子辐照之不锈钢中之汇强度，作为全面研究缺陷-汇交互作用之关键方法。 这种能力对于开发耐辐射材料至关重要。即使对于相同类型的缺陷汇，微调其微观结构，以最大限度地提高汇强度需要的知识结构和汇强度之间的一对一的相关性。 该研究将有助于对金属缺陷的全面了解。 该项目为学生提供了独特的机会，将核工程，纳米材料，原子尺度表征和原子尺度建模方面的联合收割机培训和研究结合起来，以解决现实世界中的重要问题。 对于自然富铁的铁基不锈钢，注入57 Fe同位素原子将引入57 Fe杂质。退火后，57 Fe在缺陷汇处富集的量直接反映了缺陷俘获的汇强度。因此，在不同的辐照/退火/应力条件下的缺陷下沉强度可以系统地研究。三维原子探针断层扫描（APT）将被用来映射57 Fe同位素分布。APT与透射电子显微镜（TEM）和3-D TEM层析成像相结合，以建立一对一的缺陷汇结构和汇强度之间的相关性。 该项目将研究两种缺陷下沉类型：（1）晶粒工程不锈钢中的晶界，以了解边界取向差角对下沉强度的影响;（2）氧化物弥散强化合金（ODS）中的氧化物颗粒，以了解氧化物基体界面对下沉强度的影响。该项目进一步整合了分子动力学模拟，以揭示基本原理。缺陷汇强度将被用作动力学蒙特卡罗模拟的输入，以获得结构演变，可以链接到实验观察和比较。结合材料合成，建模和原子尺度表征，该项目将获得最大限度地提高反应堆堆芯组件的辐射耐受性所需的基本理解。该项目为学生提供了独特的机会，将核工程，纳米材料，原子尺度表征和原子尺度建模方面的联合收割机培训和研究结合起来，以解决现实世界中的重要问题。

项目成果

Application of pulsed multi-ion irradiations in radiation damage research: A stochastic cluster dynamics simulation study

脉冲多离子辐照在辐射损伤研究中的应用：随机团簇动力学模拟研究

• DOI: 10.1016/j.nimb.2018.04.033
• 发表时间: 2018
• 期刊: Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
• 作者: Hoang, Tuan L.;Nazarov, Roman;Kang, Changwoo;Fan, Jiangyuan
• 通讯作者: Fan, Jiangyuan

Grain growth stagnation and texture development in an irradiated thermally stabilized nanocrystalline alloy

• DOI: 10.1063/1.5118943
• 发表时间: 2019-11
• 期刊: Journal of Applied Physics
• 影响因子: 3.2
• 作者: Prince S. Singh;Di Chen;L. Shao;Y. Picard;M. D. de Boer

The Effect of Internal Free Surfaces on Void Swelling of Irradiated Pure Iron Containing Subsurface Trenches

内部自由表面对辐照纯铁地下沟槽空洞膨胀的影响

• DOI: 10.3390/cryst9050252
• 发表时间: 2019
• 期刊: Crystals
• 影响因子: 2.7
• 作者: Wang, Tianyao;Kim, Hyosim;Garner, Frank A.;Peddicord, Kenneth L.;Shao, Lin
• 通讯作者: Shao, Lin

Dispersoid stability in ion irradiated oxide-dispersion-strengthened alloy

• DOI: 10.1016/j.jnucmat.2018.07.015
• 发表时间: 2018-10
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: Hyosim Kim;J. Gigax;Tianyi Chen;S. Ukai;F. Garner;L. Shao

Effect of Helium on Dispersoid Evolution under Self-Ion Irradiation in A Dual-Phase 12Cr Oxide-Dispersion-Strengthened Alloy

• DOI: 10.3390/ma12203343
• 发表时间: 2019-10
• 期刊: Materials
• 影响因子: 3.4
• 作者: Hyosim Kim;Tianyao Wang;J. Gigax;S. Ukai;F. Garner;L. Shao