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Phenomenological and Experimental Study of the Tritium Distribution in the Effluents Resulting from the Sodium Hydrolysis

机译:钠水解废水中flu分布的现象学和实验研究

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Within the framework of the dismantling of Sodium cooled fast neutron reactors (SFR) in France (PHENIX, SUPERPHENIX, RAPSODIE), several processes are under investigation regarding sodium disposal. One of them, called ELA (radioactive sodium waste treatment process), is based on the implementation of the sodium-water reaction, in a controlled and progressive way, to remove residual sodium mainly from the sodium purification systems called cold traps. This system contains, after draining, residual sodium and trapped impurities such as sodium oxide (Na_2O), sodium hydride (NaH) with traces of tritium (NaT). The hydrolysis of these various chemical species leads to the production of a liquid effluent, mainly composed of an aqueous solution of sodium hydroxide, and a gaseous effluent, mainly composed of an inert gas, hydrogen and steam. The tritium is present in both effluents. Within the gaseous effluent, it is expected to be released as HT form only. But, according to some experimental data gathered from tritiated sodium hydrolysis operations performed at the CEA in France, a non-negligible amount of tritium is released in the off-gas as HTO form (up to more than 90 % of the tritium found in the gaseous effluent). HTO being 10,000 times more radiotoxic than HT, a precise knowledge of the mechanisms governing the phase distribution of tritium is necessary to estimate the tritium distribution. Indeed, it will help designing the process needed to optimize the treatment of the off-gas before its release into the environment. In order to develop a numerical model able to predict the chemical composition of each effluent, a phenomenological description of the hydrolysis of residual sodium performed in the conditions of ELA has been proposed and is described in this paper. To validate some of the hypotheses made in this phenomenological description, and with the aim to validate the model that will be based on this scenario, a series of experiments has been performed in a laboratory-scale hydrolysis process designed at the CEA Cadarache, France. The experimental device consists of a 2-liter cylindrical glass reactor into which small quantities of sodium containing tritium were hydrolyzed by water injected drop by drop. A chemical characterization of the effluents generated by the process will allow us to study the influence of several parameters on the tritium distribution. An analysis of the experimental results obtained during this study is provided in this paper.
机译:在法国(PHENIX,SUPERPHENIX,RAPSODIE)的钠冷快中子反应堆(SFR)拆卸框架内,有关钠处理的几种工艺正在研究中。其中一种被称为ELA(放射性钠废物处理工艺)是基于钠-水反应的实施,以可控和渐进的方式,主要是从称为冷阱的钠纯化系统中除去残留的钠。排干后,该系统包含残留的钠和残留的杂质,例如氧化钠(Na_2O),氢化钠(NaH)和痕量的((NaT)。这些各种化学物质的水解导致产生主要由氢氧化钠水溶液组成的液体流出物和主要由惰性气体,氢气和蒸汽组成的气态流出物。两种废水中都存在。在气态流出物中,预期它仅以HT形式释放。但是,根据从法国CEA进行的sodium化钠水解操作中收集的一些实验数据,不可忽略的H气以HTO的形式释放到了废气中(高达90%的the气是从HTO中释放出来的)。气体流出物)。 HTO的放射性毒性是HT的10,000倍,因此,对于控制tri的相分布的机理的精确了解对于估算the的分布是必不可少的。实际上,这将有助于设计在废气排放到环境之前优化废气处理所需的过程。为了建立能够预测每种流出物化学组成的数值模型,已经提出了在ELA条件下进行残留钠水解的现象学描述,并在本文中进行了描述。为了验证这种现象学描述中的某些假设,并为了验证将基于此场景的模型,在法国CEA Cadarache设计的实验室规模水解过程中进行了一系列实验。实验装置由一个2升的圆柱形玻璃反应器组成,通过逐滴注入的水将少量含钠的t水解成该反应器。该过程产生的废水的化学表征将使我们能够研究几个参数对the分布的影响。本文提供了对本研究中获得的实验结果的分析。

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