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Attenuation of radioactive releases from NPP under accident conditions: An experimental research on risk-dominant scenarios

机译:事故条件下核电厂放射性释放的衰减:关于风险主导情景的实验研究

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摘要

Accident scenarios in which a nuclear power plant (NPP) containment is by-passed, may become a significant contribution to the NPP risk. The reason is the direct access to the environment that any radioactive material escaping from a degrading core would have. This is the case of steam generator tube rupture (SGTR) severe accident sequences in pressurized water reactors (PWRs), in which tube breaches in the steam generator communicate the primary system of the nuclear reactor and the environment. This paper presents the major results of an experimental investigation aimed to assess and characterize the mitigation of radioactive releases when flowing through the secondary side of a steam generator during SGTR severe accident sequences. A set of experiments performed in a mock-up tube bundle scaled from a real steam generator has demonstrated that particles are significantly retained in the region around the breach, even in the total absence of water. The tests explored the anticipated conditions in the scenario: gas jet injection, micron particles of different nature (dense spheres vs. aggregates) and tube breach types (guillotine vs. fish-mouth). The main variable affecting retention is the particle nature. The collection efficiency reached 75-95% in the case of dense spheres. The influence of natural aerosol mechanisms like inertial impaction, turbulent deposition, resuspension and fragmentation are discussed in the paper.
机译:绕过核电厂(NPP)围堵的事故场景可能会成为NPP风险的重要因素。原因是从降解核中逸出的任何放射性物质都会直接进入环境。压水堆(PWR)中蒸汽发生器管道破裂(SGTR)严重事故序列就是这种情况,其中蒸汽发生器中的管道破裂使核反应堆的主要系统与环境连通。本文介绍了一项实验研究的主要结果,旨在评估和表征在SGTR严重事故序列中流经蒸汽发生器次级侧的放射性释放。在由真实蒸汽发生器按比例缩放的模拟管束中进行的一组实验表明,即使在完全不含水的情况下,颗粒也明显保留在裂缝周围的区域中。测试探索了该场景中的预期条件:气体喷射注入,不同性质的微米颗粒(致密球体与聚集体)和管破裂类型(断头台与鱼嘴)。影响保留率的主要变量是颗粒性质。在致密球的情况下,收集效率达到75-95%。本文讨论了诸如惯性碰撞,湍流沉积,重悬和破碎等自然气溶胶机理的影响。

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