首页> 外文会议>14th International Conference on Nuclear Engineering 2006(ICONE14) vol.3 >Transient Accident Analysis of a Supercritical Carbon Dioxide Brayton Cycle Energy Converter Coupled to an Autonomous Lead-Cooled Fast Reactor
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Transient Accident Analysis of a Supercritical Carbon Dioxide Brayton Cycle Energy Converter Coupled to an Autonomous Lead-Cooled Fast Reactor

机译:超临界二氧化碳布雷顿循环能量转换器与自主铅冷快堆耦合的瞬态事故分析

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摘要

The Supercritical Carbon Dioxide (S-CO_2) Brayton Cycle is a promising advanced alternative to the Rankine saturated steam cycle and recuperated gas Brayton cycle for the energy converters of specific reactor concepts belonging to the U.S. Department of Energy Generation IV Nuclear Energy Systems Initiative. A new plant dynamics analysis computer code has been developed for simulation of the S-CO_2 Brayton cycle coupled to an autonomous, natural circulation Lead-Cooled Fast Reactor (LFR). The plant dynamics code was used to simulate the whole-plant response to accident conditions. The specific design features of the reactor concept influencing passive safety are discussed and accident scenarios are identified for analysis. Results of calculations of the whole-plant response to loss-of-heat sink, loss-of-load, and pipe break accidents are demonstrated. The passive safety performance of the reactor concept is confirmed by the results of the plant dynamics code calculations for the selected accident scenarios.
机译:对于属于美国能源部IV核能系统计划的特定反应堆概念的能量转换器而言,超临界二氧化碳(S-CO_2)布雷顿循环是一种有前景的朗肯饱和蒸汽循环和回热气体布雷顿循环的先进替代方案。已经开发了一种新的工厂动力学分析计算机代码,用于模拟与自主,自然循环铅冷却快堆(LFR)耦合的S-CO_2布雷顿循环。工厂动态代码用于模拟整个工厂对事故情况的响应。讨论了影响被动安全的反应堆概念的具体设计特征,并确定了发生事故的情况以进行分析。展示了整个工厂对散热损失,负载损失和管道破裂事故的响应的计算结果。反应堆概念的被动安全性能已通过针对选定事故场景的工厂动力学代码计算结果得到证实。

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