Filtered Containment Venting System (FCVS) for removal of elemental and organic iodine during severe nuclear power plant accidents

T. Solaija, N. Irfan, K. Qureshi, K. Waheed, A. Farooq, M. Ahmad
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引用次数: 4

Abstract

Structural integrity may be threatened due to over pressurization by accumulation of steam and noncondensable gases in a scenario of ‘beyond design basis accident’ leading to a situation of potential fission product release to the environment. Filtered Containment Venting System (FCVS) has been considered for depressurization while keeping off-site doses low or within prescribed limits. Various types of FCVS have been installed on many nuclear power plants world-wide. In case of a nuclear meltdown accident followed by an over-pressurization that may require venting, the mixture of steam and non-condensable gases containing iodine is passed through the FCVS. Radioactive iodine in various organic and inorganic forms is scrubbed in a specific scrubbing solution while the cleaned steam-gas mixture can then be discharged into the environment. Among the spectrum of fission nuclides generated as a result of fission, iodine with its nine oxidation stages is perhaps the most reactive fission product generated and released into the primary coolant system during the event of severe NPP accidents. Because of fuel degradation and melting, a huge inventory of iodine is volatilized. Understanding of iodine behavior in environment similar to that of containment is necessary prerequisite for planning effective mitigation system for efficient retention of iodine within containment boundary. The prevailing conditions i.e. iodine concentration, pH, temperature and dose rate will govern the iodine behavior in the sump water as well as in the containment. Development of an efficient, fast and reliable mechanism to retain volatile iodine species in a containment of a nuclear reactor during a severe accident has been an active area of research in the recent years. The need for such research is greatly enhanced in Post Fukushima nuclear era. This paper reviews the available FCVS options and specifically outlines the related research and development activities being carried out at Pakistan Institute of Engineering & Applied Sciences (PIEAS).
过滤式安全壳排气系统(FCVS)用于在核电站严重事故中去除元素碘和有机碘
在“超出设计基础事故”的情况下,由于蒸汽和不凝性气体积聚的过压,导致潜在的裂变产物释放到环境中,结构完整性可能受到威胁。过滤安全壳排气系统(FCVS)被认为是减压,同时保持场外剂量低或在规定范围内。世界上许多核电站都安装了各种类型的燃料电池电池。在核熔毁事故发生后,由于压力过大,可能需要排气,蒸汽和含有碘的不可冷凝气体的混合物通过fcv。各种有机和无机形式的放射性碘在特定的洗涤溶液中洗涤,而清洗后的蒸汽-气体混合物可以排放到环境中。在因裂变而产生的裂变核素谱中,具有九个氧化阶段的碘可能是在发生严重核电站事故时产生并释放到一次冷却剂系统中的最活跃的裂变产物。由于燃料的降解和熔化,大量的碘被挥发。了解碘在与安全壳相似的环境中的行为是规划有效的减缓系统以在安全壳边界内有效保留碘的必要前提。现行条件,即碘浓度、pH值、温度和剂量率将决定碘在污水和安全壳中的行为。近年来,开发一种有效、快速和可靠的机制,在发生严重事故时将挥发性碘保留在核反应堆的安全壳内,一直是一个活跃的研究领域。在后福岛核时代,对这类研究的需求大大增强。本文回顾了现有的FCVS选项,并特别概述了巴基斯坦工程与应用科学研究所(PIEAS)正在进行的相关研究和开发活动。
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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