Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
V. Chakin, R. Rolli, R. Gaisin, W. Van Renterghem
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引用次数: 0

Abstract

The present study investigated the release of tritium from beryllium irradiated at 323 K to a neutron fluence of 4.67 × 1026 m−2 (E > 1 MeV), corresponding up to 22,000 appm helium and 2000 appm tritium productions. The TPD tests revealed a single tritium release peak during thermal desorption tests, irrespective of the heating mode employed. The tritium release peaks occurred at temperatures ranging from 1031–1136 K, depending on the heating mode, with a desorption energy of 1.6 eV. Additionally, the effective tritium diffusion coefficient was found to vary from 1.2 × 10−12 m2/s at 873 K to 1.8 × 10−10 m2/s at 1073 K. The evolution of beryllium microstructure was found to be dependent on the annealing temperature. No discernible differences were observed between the as-received state and after annealing at 473–773 K for 5 h, with a corresponding porosity range of 1–2%. The annealing at temperatures of 873–1373 K for 5 h resulted in the formation of large bubbles, with porosity increasing sharply above 873 K and reaching 30–60%.
低温至高中子剂量辐照铍在BR2反应堆中的氚解吸行为及微观结构演变
本研究研究了铍在323 K辐照下释放氚的中子通量为4.67 × 1026 m−2 (E > 1 MeV),对应于22,000 appm氦和2000 appm氚的产量。TPD测试显示,在热脱附测试中,无论采用何种加热模式,都有一个单一的氚释放峰。氚的释放峰发生在1031-1136 K的温度范围内,取决于加热模式,解吸能为1.6 eV。此外,氚的有效扩散系数在873 K时为1.2 × 10−12 m2/s,在1073 K时为1.8 × 10−10 m2/s。铍微观结构的演化与退火温度有关。在473-773 K下退火5 h后,气孔率范围为1-2%,接收态与退火后无明显差异。在873 - 1373 K温度下退火5 h,形成大气泡,孔隙率在873 K以上急剧增加,达到30-60%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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