Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan
Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan
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DOI：
10.1016/j.jnucmat.2020.152506
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发表时间：
2021
影响因子：
3.1
通讯作者：
S. Nogami;A. Hasegawa;M. Fukuda;M. Rieth;J. Reiser;G. Pintsuk
中科院分区：
文献类型：
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作者：
S. Nogami;A. Hasegawa;M. Fukuda;M. Rieth;J. Reiser;G. Pintsuk
W材料作为聚变反应器转向器等离子体表面材料（PFM）的力学性能存在低温脆性、高韧脆转变温度（DBTT）和再结晶引起的脆性等缺陷。为了解决这些问题，在过去的十年中，在日本大学的合作研发下，开发了具有更好的热机械性能，中子辐照耐受性和大规模生产微结构均匀性的W材料。本文从材料的短期和长期性能和现象，包括中子辐照和高热负荷的影响等方面，讨论了晶粒细化、k掺杂、la2o3粒子弥散强化、Re合金化等在实际核聚变反应堆环境下需要考虑的影响。通过这一研究，k掺杂和再加成显示出一些积极的效果。在本研究开发的材料中，掺杂k的W-3%Re热轧板可能是PFM的较好解决方案，从几个方面显示出优越的性能。然而，稀土合金材料在较高剂量的中子辐照下存在较高的辐照硬化问题。因此，研究高剂量中子辐照下的热力学性能是实现聚变反应堆长期结构可靠性和寿命的迫切需要。
There remain some drawbacks of mechanical properties of W materials as a plasma facing material (PFM) for fusion reactor divertors, which are low temperature brittleness, high ductile-to-brittle transition temperature (DBTT), and recrystallization-induced embrittlement. To solve these issues, development of W materials with improved thermo-mechanical properties, neutron irradiation tolerance, and possibility of mass-production with microstructural uniformity has been advanced for the last decade under the collaboration R&D by universities in Japan. In this paper, the effects of grain refining, K-doping, dispersion strengthening by La2O3particles, and alloying by Re are discussed from the viewpoints of both short- and long-term material properties and phenomena, including effects of neutron irradiation and high heat loads, which should be considered under the actual fusion reactor environments. Through this R&D, K-doping and Re-addition showed several positive effects. Among the materials developed in this R&D, K-doped W-3%Re hot-rolled plate could be a better solution for PFM, which demonstrated superior properties from several perspectives. However, materials alloyed by Re have an intrinsic concern of higher irradiation hardening caused by neutron irradiation up to higher doses. Therefore, it is pointed out that investigations of thermo-mechanical properties under higher dose neutron irradiation are significantly required to realize long-term structural reliability and lifetime of fusion reactors.