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Numerical simulations of an innovative decay heat removal systems

机译:创新衰减散热系统的数值模拟

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摘要

The general interest in innovative forms of nuclear energy from fission leads many industrial companies and research institutions to develop ambitious projects to design an innovative reactor fleet. Often such new designs are based on innovative reactor coolants and imply as a consequence a complete change of the technology know how. Among the main characteristics of such developments, safety demonstration plays a central role. Safety systems of such newly developed designs must meet different requirements respect to those designed for reactors currently in operation. One good example is the case of the lead fast reactor, where primary coolant freezing must be considered. The paper reports an excursus of what has been done over the past few years on ALFRED reactor decay heat removal system, reporting the history of the safety system from the preliminary configuration up to the present, together with an innovative idea of a passive system to delay lead freezing. Finally, ongoing activities for the experimental qualification of such safety system are presented, together with support and pretest calculations.
机译:来自裂变的创新形式的核能的一般兴趣导致许多工业公司和研究机构开发雄心勃勃的项目设计创新的反应堆舰队。通常,这种新设计基于创新的反应堆冷却剂,并且由于这种技术的完整变化知道如何。在这种发展的主要特征中,安全示范起着核心作用。这种新开发设计的安全系统必须符合目前运营中专为反应堆设计的不同要求。一个很好的例子是引线快速反应器的情况,必须考虑一次冷却剂冷冻。本文报告了过去几年在阿尔弗雷德反应堆衰变散热系统上完成的事件的潜品,从初步配置向现在报告了安全系统的历史以及被动系统延迟的创新理念引导冻结。最后,展示了这种安全系统的实验资格的持续活动,以及支持和预测试。

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