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Studies on the behaviour of tritium in components and structure materials of tritium confinement and detritiation systems of ITER

机译:ITER of限制和破坏体系components和结构材料中of的行为研究

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Confinement and the removal of tritium are key subjects for the safety of ITER. The ITER buildings are confinement barriers of tritium. In a hot cell, tritium is often released as vapour and is in contact with the inner walls. The inner walls of the ITER tritium plant building will also be exposed to tritium in an accident. The tritium released in the buildings is removed by the atmosphere detritiation systems (ADS), where the tritium is oxidized by catalysts and is removed as water. A special gas of SF_6 is used in ITER and is expected to be released in an accident such as a fire. Although the SF_6 gas has potential as a catalyst poison, the performance of ADS with the existence of SF_6 has not been confirmed as yet. Tritiated water is produced in the regeneration process of ADS and is subsequently processed by the ITER water detritiation system (WDS). One of the key components of the WDS is an electrolysis cell. To overcome the issues in a global tritium confinement, a series of experimental studies have been carried out as an ITER R&D task: (1) tritium behaviour in concrete; (2) the effect of SF_6 on the performance of ADS and (3) tritium durability of the electrolysis cell of the ITER-WDS. (1) The tritiated water vapour penetrated up to 50 mm into the concrete from the surface in six months' exposure. The penetration rate of tritium in the concrete was thus appreciably first, the isotope exchange capacity of the cement paste plays an important role in tritium trapping and penetration into concrete materials when concrete is exposed to tritiated water vapour. It is required to evaluate the effect of coating on the penetration rate quantitatively from the actual tritium tests. (2) SF_6 gas decreased the detritiation factor of ADS. Since the effect of SF_6 depends closely on its concentration, the amount of SF_6 released into the tritium handling area in an accident should be reduced by some ideas of arrangement of components in the buildings. (3) It was expected that the electrolysis cell of the ITER-WDS could endure 3 years' operation under the ITER design conditions. Measuring the concentration of the fluorine ions could be a promising technique for monitoring the damage to the electrolvsis cell.
机译:限制和去除tri是国际热核实验堆安全的关键课题。国际热核实验堆建筑物是of的隔离屏障。在热室中,tri经常以蒸气形式释放并与内壁接触。 ITER plant工厂厂房的内壁在发生事故时也将暴露于tri中。建筑物中释放的通过大气破坏系统(ADS)去除,where在其中被催化剂氧化并作为水去除。在国际热核实验堆中使用了一种特殊的SF_6气体,它有望在发生火灾等事故时释放出来。尽管SF_6气体有可能成为催化剂毒物,但尚未确认存在SF_6的ADS的性能。在ADS的再生过程中会产生ti化水,然后由ITER水处理系统(WDS)处理。 WDS的关键组件之一是电解池。为了克服全球tri限制的问题,作为ITER的研发任务已进行了一系列实验研究:(1)混凝土中behavior的行为; (2)SF_6对ADS性能的影响和(3)ITER-WDS电解槽的tri耐久性。 (1)暴露六个月后,The化的水蒸气从表面渗透至混凝土的最大深度为50毫米。因此首先要注意tri在混凝土中的渗透率,当混凝土暴露于tri化水蒸气中时,水泥浆的同位素交换能力在tri的捕获和渗入混凝土材料中起着重要作用。需要从实际的tests测试中定量评估涂层对渗透率的影响。 (2)SF_6气体降低了ADS的破坏因子。由于SF_6的影响密切取决于其浓度,因此应通过一些建筑物中组件的布置思路来减少事故中释放到handling处理区域中的SF_6的量。 (3)预期在ITER设计条件下,ITER-WDS的电解池可以运行3年。测量氟离子的浓度可能是一种有前途的技术来监测对电蚀细胞的损伤。

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