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铍及铍合金在高剂量氦离子辐照下的起泡行为

Blistering Behavior of Beryllium and Beryllium Alloy under High-Dose Helium Ion Irradiation.

作者信息

Liu Ping-Ping, Wang Qi-Cong, Jia Yu-Mei, Han Wen-Tuo, Yi Xiao-Ou, Zhan Qian, Wan Fa-Rong

机构信息

School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China.

USTB-BJHB Joint Laboratory of Beryllium and Advanced Materials for Fusion Energy, University of Science and Technology Beijing, Beijing 100083, China.

出版信息

Materials (Basel). 2024 Aug 11;17(16):3997. doi: 10.3390/ma17163997.

DOI:10.3390/ma17163997
PMID:39203173
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC11356760/
Abstract

Beryllium (Be) has been selected as the solid neutron multiplier material for a tritium breeding blanket module in ITER, which is also the primary option of the Chinese TBM program. But the irradiation swelling of beryllium is severe under high temperature, high irradiation damage and high doses of transmutation-induced helium. Advanced neutron multipliers with high stability at high temperature are desired for the demonstration power plant (DEMO) reactors and the China Fusion Engineering Test Reactor (CFETR). Beryllium alloys mainly composed of BeM (M is W or Ti) phase were fabricated by HIP, which has a high melting point and high beryllium content. Beryllium and beryllide (BeTi and BeW) samples were irradiated by helium ion with 30 keV and 1 × 10 cm at RT. The microstructures of Be, BeTi and BeW samples were analyzed by SEM and TEM before and after ion irradiation. The average size of the first blistering on the surface of Be-W alloy is about 0.8 μm, and that of secondary blistering is about 79 nm. The surface blistering rates of the beryllium and beryllide samples were also compared. These results may provide a preliminary experimental basis for evaluating the irradiation swelling resistance of beryllium alloy.

摘要

铍（Be）已被选为国际热核聚变实验堆（ITER）中氚增殖包层模块的固体中子倍增材料，这也是中国全尺寸模块（TBM）计划的主要选择。但是在高温、高辐照损伤和高剂量嬗变产生的氦的作用下，铍的辐照肿胀严重。对于示范电站（DEMO）反应堆和中国聚变工程试验堆（CFETR），需要高温下具有高稳定性的先进中子倍增材料。通过热等静压（HIP）制备了主要由BeM（M为W或Ti）相组成的铍合金，其具有高熔点和高铍含量。在室温下，用能量为30 keV、通量为1×10 cm的氦离子辐照铍及铍化物（BeTi和BeW）样品。在离子辐照前后，通过扫描电子显微镜（SEM）和透射电子显微镜（TEM）分析了Be、BeTi和BeW样品的微观结构。Be-W合金表面首次起泡的平均尺寸约为0.8μm，二次起泡的平均尺寸约为79nm。还比较了铍及铍化物样品的表面起泡率。这些结果可为评估铍合金的抗辐照肿胀性能提供初步的实验依据。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/dec0f136ee4f/materials-17-03997-g010.jpg
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https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/07408ec15530/materials-17-03997-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/41128d71d4ab/materials-17-03997-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/dec0f136ee4f/materials-17-03997-g010.jpg
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https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/8171f2767def/materials-17-03997-g006.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/dc7db213186c/materials-17-03997-g007.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/07408ec15530/materials-17-03997-g008.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/41128d71d4ab/materials-17-03997-g009.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/c9df/11356760/dec0f136ee4f/materials-17-03997-g010.jpg

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本文引用的文献

1
Hydrogen and helium trapping in hcp beryllium.六方密排铍中氢和氦的捕获
Commun Chem. 2023 Apr 21;6(1):76. doi: 10.1038/s42004-023-00877-7.
2
New insights into microstructure of irradiated beryllium based on experiments and computer simulations.基于实验和计算机模拟对辐照铍微观结构的新见解。
Sci Rep. 2020 May 15;10(1):8042. doi: 10.1038/s41598-020-64654-5.