偏滤器用钨基材料的热负荷损伤行为研究进展
收稿日期: 2024-09-03
修回日期: 2025-01-12
网络出版日期: 2025-05-07
基金资助
国家重点研发计划项目(2019YFE03120002);国家重点研发计划项目(2022YFE03140001);国家重点研发计划项目(2022YFE03030003);中央高校基本科研业务费专项资金项目(JZ2023HGQB0164);国家资助博士后研究人员计划项目(GZC20230656);安徽省自然科学基金项目(2108085J21);安徽省自然科学基金项目(2308085QE154);安徽省重点研发计划项目(202104A05020045)
Research Progress on Heat Load Damage Behavior of Tungsten-Based Materials for Divertor
Received date: 2024-09-03
Revised date: 2025-01-12
Online published: 2025-05-07
Supported by
National Key Research and Development Program of China(2019YFE03120002);National Key Research and Development Program of China(2022YFE03140001);National Key Research and Development Program of China(2022YFE03030003);Fundamental Research Funds for the Central Universities(JZ2023HGQB0164);Postdoctoral Fellowship Program of CPSF(GZC20230656);Natural Science Foundation of Anhui Province(2108085J21);Natural Science Foundation of Anhui Province(2308085QE154);Key Research and Development Program of Anhui Province(202104A05020045)
有限的能源无法满足人类社会长期发展的需求，核聚变能源被视为保护环境和满足未来能源需求的重要解决方案之一。然而，为确保聚变堆的正常运行，解决托卡马克(Tokamak)装置中面向等离子体的偏滤器热负荷损伤问题至关重要。W因具有高熔点、低物理溅射率、低氘滞留以及优异的力学性能等优点而成为核聚变堆中偏滤器部位首选的面向等离子体材料(PFMs)。在聚变堆运行期间，钨基PFMs会受到持续的热负荷损伤，通常偏滤器部位需承受5~20 MW/m2高热峰值的稳态热负荷和功率密度高达约2 GW/m2的瞬态热负荷。因此，W在热负荷作用下的损伤行为及抑制损伤策略已成为当前研究的热点问题。本文根据国内外现有研究成果，阐述了纯W、合金化钨、弥散强化钨在热负荷作用下的损伤行为。针对钨基材料的热负荷损伤演变情况及抑制损伤策略进行总结与展望，进而为后续研究工作提供参考。
罗来马 , 陈宇 , 姚刚 , 朱晓勇 , 朱大焕 , 吴玉程 . 偏滤器用钨基材料的热负荷损伤行为研究进展[J]. 金属学报, 2025 , 61(7) : 961 -978 . DOI: 10.11900/0412.1961.2024.00309
Limited energy resources cannot meet the long-term developmental needs of human society. As such, nuclear fusion energy is considered a key solution for environmental protection and meeting future energy demands. However, to ensure the reliable operation of fusion reactors, addressing heat load damage to the divertor facing plasma in tokamak devices is crucial. The divertor, an indispensable core component of fusion devices, plays essential roles in these devices, including the removal of heat load generated via scraping layers and radiation and protection of the main vacuum chamber, auxiliary heating systems, and diagnostic systems, thereby ensuring the safe and stable operation of nuclear fusion reactors. Nevertheless, due to harsh operational conditions, the divertor is prone to damage, limiting the stable operation of long-pulse, high-parameter plasmas. W is critical in the divertor of fusion reactors, primarily owing to its high melting point, low physical sputtering rate, low deuterium retention, and excellent mechanical properties, allowing it to perform stably under extreme conditions. However, tungsten materials have several limitations, including a high ductile-brittle transition temperature, a low recrystallization temperature, and susceptibility to activation. Therefore, it is necessary to regulate, modify, and optimize these materials to enhance the performance of plasma-facing materials (PFMs). Such improvements aim to increase their resilience under extreme environments, minimize damage risks under high heat loads, and enhance heat load resistance, thereby ensuring the long-term stable operation of the divertor in fusion reactors and to meet future energy challenges. The working conditions of fusion reactors are extremely harsh, with the divertor region experiencing continuous heat load damage. It typically faces steady-state heat loads with peak values as high as 5-20 MW/m2 and transient heat loads of up to ~2 GW/m2. These heat loads can cause melting and cracking on both sides of the divertor cassette, posing a risk of reactor failure. Consequently, the study of the heat load damage behavior in tungsten-based PFMs as well as development of damage mitigation strategies have become hot topics in fusion research. This paper reviews current research efforts, both domestic and international, related to the damage behavior of pure tungsten, tungsten alloys, and dispersed phase-strengthened tungsten under heat load conditions. Additionally, it summarizes and forecasts the evolution of heat load damage in tungsten-based materials and presents strategies for damage mitigation, thereby providing a reference for future research endeavors.
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