作为核反应堆的核心材料长期使用后,SAV-1合金和结构Fe-Cr-Ni钢的结构和机械性能发生了变化
Alexey Dikov1, Sergey Kislitsin1, Boris Ivanov1
1Institute of Nuclear Physics, Ministry of Energy of the Republic of Kazakhstan, Almaty 050032, Kazakhstan.
Materials (Basel, Switzerland)
|July 30, 2025
概括
像BN-350和WWR-K这样老化的核反应堆中的结构材料显示出显著的降解. 本研究评估了它们的条件,以支持延长早期一代核电和研究反应堆的使用寿命.
科学领域:
- 核工程 核工程是指核工程.
- 材料科学 材料科学 材料科学
背景情况:
- 大多数正在运行的核反应堆都是早期的,并且已经超过了其设计寿命.
- 延长反应堆的使用寿命至关重要,但取决于材料的结构完整性.
- 评估材料降解是确保安全,延长反应堆运行的关键.
研究的目的:
- 评估BN-350快中子和WWR-K研究反应堆中的结构材料的降解.
- 提供支持早期核反应堆使用寿命延长的数据.
- 了解长期中子辐射对材料性能的影响.
主要方法:
- 在WWR-K反应堆经过56年的运行后,对来自WWR-K反应堆的SAV-1合金的目击样本进行分析.
- 辐射和未辐射SAV-1合金的机械性质测试 (收益强度,抗拉强度,延长)
- 在老化合金中检测二级阶段沉的微结构检查.
- 在350-450°C的电力反应堆辐射结构钢的研究.
主要成果:
- 被辐射的SAV-1合金表现出降低的收益强度 (24-48%) 和拉伸强度,延长变化最小 (~2%).
- 在SAV-1合金颗粒和边界中观察到富含的二次相粒子,表明老化.
- 受辐射的结构钢由于分散硬化和霍尔-佩奇效应而表现出硬化和缓解爬行行为.
结论:
- 长期运行大大降低了核反应堆核心材料的机械性能.
- 了解材料降解机制对于安全延长核反应堆寿命至关重要.
- 这些发现支持对早期反应堆持续运行的材料状况评估的需求.
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