氟盐冷却高温堆氚输运特性分析程序开发
首发时间:2017-05-25
摘要:氟盐冷却高温堆(Fluoride-salt-cooled High-temperature Reactor, FHR)是第四代核能系统熔盐堆的衍生堆型,它具有高安全性、高经济性等优点。氚的控制是限制其发展的关键问题,要实现氚的有效控制,首先要明确氚在熔盐堆中的输运行为。文章介绍了氚在熔盐堆一回路中的输运特性,包括氚的产生及存在形态的分化、石墨对氚的吸附、氚在熔盐中的溶解与扩散以及氚在管壁材料中的渗透等。针对氚在熔盐堆中的输运行为,结合FHR的结构特点与运行工况,建立了数学物理模型,基于FORTRAN程序设计语言开发了适用于FHR的氚输运特性分析程序TAPAS(Tritium trAnsPort chAracteristicS in FHR)。通过将实验数据与程序计算结果对比,说明了TAPAS程序计算的合理性和准确性,为后续熔盐堆氚控特性分析提供了软件支撑。
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Development of Tritium Transport Characteristics Analysis Code for Fluoride-salt-cooled High-temperature Reactor
Abstract:Fluoride-salt-cooled High-temperature Reactor (FHR) is a branch of Molten Salt Reactors (MSR), belonging to generation IV reactors. It has remarkable advantages in safety and economics. Tritium control is one of the pivotal issues which confine the development of FHR. In order to control tritium effectively, the transport characteristics of tritium in fluoride salt must be known. In this paper, the transport characteristics of tritium in the primary loop of FHRs were expounded, including tritium production and speciation, the absorption and desorption by graphite, dissolution and diffusion in molten salt and permeation through structural materials. Considering the construction features and operational states of FHRs, a series of reasonable mathematical and physical models for tritium transport characteristics analysis of FHR were established, and then the tritium transport characteristics analysis code (TAPAS) for FHRs has been developed based on FORTRAN code. The preliminary verification of the code has been conducted against empirical data, and the results proved the fidelity and accuracy of TAPAS.
Keywords: Nuclear Science and Engineering FHR Tritium transport characteristics
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No.4733798120101014****
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