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Modification of the Core Cooling System of TRIGA 2000 Reactor

机译:Triga 2000反应器芯冷却系统的修改

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To accomplish safety requirements, a set of actions has to be performed following the recommendations of the IAEA safety series 35 applied to research reactor. Such actions are considered in modernization of the old system, improving the core cooling system and safety evaluations. Due to the complexity of the process and the difficulty in putting the apparatus in the reactor core, analytical and experimental study on the determination of flow and temperature distribution in the whole coolant channel are difficult to be done. In the present work, a numerical study of flow and temperature distribution in the coolant channel of TRIGA 2000 has been carried out using CFD package. For this study, simulations were carried out on 3-D tested model. The model consists of the reactor tank, thermal and thermal izing column, reflector, rotary specimen rack, chimney, fuel element, primary pipe, diffuser, beam tube and a part of the core are constructed by 1.50 million unstructured tetrahedral cell elements. The results show that for the initial condition (116 fuel elements in the core) and for the inlet temperature of 24°C and the primary velocity of 5.6 m/s, there no boiling phenomena occur in the coolant channel. Due to this result, it is now possible to improve the core cooling system of TRIGA 2000 reactor. Meanwhile, forced flow from the diffuser system only affected the flow pattern in the outside of chimney and put on a small effect to the fluid flow's velocity in the inside of chimney.
机译:为了达到安全要求,一组动作有以下应用研究反应堆原子能机构安全系列35的建议进行。这样的动作在旧体制的现代化认为,提高核心冷却系统和安全评估。由于该过程的复杂性和在投入反应堆芯的装置中的困难,在整个冷却剂通道流动和温度分布的测定分析和实验研究是难以完成的。另外,在本工作中,在2000 TRIGA的冷却剂通道流动和温度分布的数值研究已经进行了使用CFD包。对于本研究,模拟,3-d测试模型进行。该模型由反应器罐,热和热定义柱,反射镜,旋转试样架,烟囱,燃料元件,主管,漫射器,束管和芯的一部分被1.50百万非结构化四面体单元元件构成的。结果表明,初始条件(在芯116个的燃料元件)和24℃的入口温度和5.6米/秒的主要速度,还有发生在冷却剂通道中没有沸腾的现象。由于这一结果,现在有可能改善TRIGA 2000反应堆的堆芯冷却系统。另一方面,从扩散器系统强制流仅影响在烟囱的外部的流动模式和在烟囱的内部放在一个小的影响到流体流动的速度。

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