聚变堆金属材料中子辐照多尺度计算模拟

中子辐照条件下材料结构与性能是中国聚变工程实验堆（CFETR）以及未来聚变反应堆工程设计的重要依据。钨材料是CFETR拟全面使用的壁材料，但中子辐照导致钨硬度升高和韧性大幅下降，严重影响材料的服役性能，进而影响CFETR运行的安全性和稳定性。在目前缺乏聚变中子源进行辐照实验的情况下，开展聚变堆材料中子辐照模拟研究显得愈发重要和紧迫。在国家磁约束核聚变能发展研究专项的支持下，本文以钨为模型材料，构建金属材料聚变中子辐照模拟平台，解决中子辐照模拟的共性关键技术问题，实现中子级联损伤→辐照微结构→力热性能的多尺度模拟，籍此预测聚变中子辐照条件下材料的行为。

Multiscale Modeling and Simulation of Fusion Metallic Material under Neutron Irradiation

The structure and property of materials under neutron irradiation is an important basis in the engineering design of China Fusion Engineering Testing Reactor (CFETR). Tungsten (W) is considered as the most promising candidates of plasma facing materials (PFMs) in CFETR, while neutron irradiation can lead to an increase in hardness and a decrease in toughness of W-PFMs, seriously affecting the safety and stability of CFETR. Due to the lack of fusion neutron sources, the modelling and simulation of defect structure and corresponding mechanical properties of fusion materials under neutron irradiation are of essential significance. With the support of national key R&D program, W as the model material is taken to establish a simulation platform for neutron irradiation in metals. This platform will address the common and critical technical problems in the modeling and simulation of neutron-irradiated materials, and realize the multiscale modeling for fusion materials from neutron-induced displacement cascade to microstructure and thermal/mechanical property. Based on the platform, the performance of materials after fusion neutron irradiation can be predicted.