开发一个新的稳态热液压和安全分析代码,OpenTHY,用于TRIGA MARK II研究反应堆
S Oulad-Belayachi1, Y Boulaich2, T El Bardouni1
1Radiations and Nuclear Systems Group, FS, Abdelmalek Essaadi University, Tetouan, Morocco.
概括
开发了一个新的计算机代码,OpenTHY,用于TRIGA反应堆的热液压安全分析. 它通过模拟自然对流冷却和防止层故障来确保安全运行,并根据实验数据验证结果.
科学领域:
- 核工程 核工程是指核工程.
- 热水力学 热水力学
- 计算流体动力学的流体动力学.
背景情况:
- 准确的热液压分析对于核反应堆的安全至关重要.
- 现有的代码可能缺乏针对特定反应堆设计的详细建模能力,如TRIGA.
- 自然对流冷却是研究反应堆的一个关键安全特征.
研究的目的:
- 开发和验证一个新的计算代码,OpenTHY,用于对TRIGA研究反应堆进行详细的热液压安全分析.
- 为了模拟自然对流的冷却效率,并确保达到安全运行限制.
- 为了研究杆存在对燃料元件完整性的影响.
主要方法:
- 开发了OpenTHY代码,详细分辨了燃料元件 (外,间隙,燃料,杆).
- 单通道热液压模型的应用和热传递和临界热量流的确定的相关性.
- 对OpenTHY结果与实验温度测量结果的验证和与PARET/ANL代码的比较.
主要成果:
- 在自然对流下,OpenTHY成功模拟了TRIGA反应堆的热液压参数.
- 计算的温度概况仍在安全分析报告中定义的安全限值内.
- 与核沸比率 (MDNBR) 的最小偏差明显高于1.3的设计极限.
结论:
- OpenTHY代码为TRIGA反应堆的热液压安全分析提供了可靠的工具.
- 摩洛哥的TRIGA反应堆在自然对流冷却条件下安全运行.
- 该代码能够考虑杆,这提高了它在防止覆盖器故障方面的适用性.
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