氚
氢
氘
奥氏体
聚变能
融合
材料科学
氢同位素
同位素
核工程
化学
冶金
核物理学
微观结构
物理
等离子体
工程类
哲学
有机化学
语言学
作者
Т. А. Шишкова,А. В. Голубева,M. B. Rozenkevich
标识
DOI:10.1134/s0036024423100205
摘要
A summary is presented of results from studying the transport characteristics of hydrogen isotopes in a number of fusion reactor materials as ferritic–martensitic steels, austenitic steels, and CuCrZr–bronze. The parameters of tritium transport in the materials are obtained using experimentally measured parameters of hydrogen and deuterium transport within the classical rate theory. The applicability of this approach is discussed. It is shown that a considerable part of the experimental data is inconsistent with assumptions based on the classical theory. Other approaches are required to accurately predict tritium fluxes through fusion reactor materials.
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