Oxide layer formation in reduced activation ferritic steel F82H under DEMO reactor blanket condition
Oxide layer formation in reduced activation ferritic steel F82H under DEMO reactor blanket condition
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DEMO 反应堆覆盖条件下还原活化铁素体钢 F82H 中氧化层的形成
DOI：
10.1016/j.fusengdes.2019.02.129
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发表时间：
2019
影响因子：
1.7
通讯作者：
The Joint Special Design Team for DEMO
中科院分区：
文献类型：
--
作者：
Keisuke Kimura;Jumpei Mochizuki;Seira Horikoshi;Moeki Matsunaga;Hikari Fujita;Kouhei Okitsu;Teruya Tanaka;Yoshimitsu Hishinuma;Yoshiteru Sakamoto;Youji Someya;Hirofumi Nakamura;Takumi Chikada;The Joint Special Design Team for DEMO
从燃料损失和放射性危害的角度来看，氚渗透聚变包层系统中的结构材料是一个关键问题。在之前的研究中，研究了还原活化铁素体/马氏体钢中详细的氢同位素渗透行为；然而，在实际DEMO反应堆条件下，预计钢表面会发生氧化，从而改变氚渗透行为。在这项研究中，研究了在模拟环境条件下热处理的钢中氘的渗透情况，以便更精确地预测 DEMO 反应堆包层中的氚损失。低活化铁素体/马氏体钢 F82H 基体在含有 1%vol% 氢气的氦气流中在 300、400 和 500℃下热处理 100 和 200h，以模拟固体增殖反应堆 DEMO 反应堆覆盖条件。对热处理样品进行表面观察和分析后，进行气体驱动的氘渗透测量。样品表面形成氧化铁层，氧化铁层厚度为50nm～12μm。在 500°C 下热处理 100h 的样品表面上的氧化层使氘渗透降低了 5 倍。渗透测试后，确认了氧化层的消散。
Tritium permeation through structure materials in fusion blanket systems is a critical issue from the perspectives of fuel loss and radiological hazard. In the previous studies, detailed hydrogen isotope permeation behaviors in reduced activation ferritic/martensitic steels have been investigated; however, oxidation of the steel surface is expected under an actual DEMO reactor condition, and then the tritium permeation behavior will be changed. In this study, deuterium permeation through the steels heat-treated under simulated environment conditions has been investigated for more precise predictions of tritium loss at DEMO reactor blankets. Reduced activation ferritic/martensitic steel F82H substrates were heat-treated in helium gas flow containing 1 vol% hydrogen at 300, 400 and 500 °C for 100 and 200 h to simulate a solid breeder DEMO reactor blanket condition. After surface observation and analysis for the heat-treated samples, gas-driven deuterium permeation measurements were performed. An iron oxide layer was formed on the sample surface, and the thickness of the layer was 50 nm‒12 μm. The oxide layer on the sample surface heat-treated at 500 °C for 100 h decreased deuterium permeation by a factor of 5. After the permeation tests, dissipation of the oxide layers was confirmed.
影响因子：
0.9
作者：
T. Chikada;A. Suzuki;H. Maier;T. Terai;T. Muroga
通讯作者：
T. Muroga
影响因子：
1.7
作者：
H. Yamasaki;H. Kashimura;Shohei Matsuda;T. Kanazawa;T. Hanada;K. Katayama;S. Fukada;M. Nishikawa
通讯作者：
M. Nishikawa