Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Koji Morita, W. Liu, T. Arima, Yuji Arita, Isamu Sato, H. Matsuura, Y. Sekio, H. Sagara, Masatoshi Kawashima
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引用次数: 0

Abstract

Following the Fukushima Nuclear Power Plant accident in 2011, it has become increasingly important for reactor safety designs to consider measures that can prevent the occurrence of severe accidents. This report proposes a novel subassembly-type passive reactor shutdown device that expands the diversity and robustness of core disruptive accident prevention strategies for sodium-cooled fast reactors. The developed device contains pins with a fuel material that is in the solid state during normal operation but melts into a liquid when the temperature exceeds a certain value (i.e., during a potential accident). When an unprotected loss of flow (ULOF) or unprotected transient overpower (UTOP) accident occurs, the device can passively provide significant negative reactivity by rapidly transferring liquefied device fuel into the lower plenum region of the pins via gravitation alone. The reactors containing some of the proposed devices in place of original fuel subassemblies become subcritical before the driver fuels are damaged, even if ULOF or UTOP transient events occur. The present study evaluates candidate materials for device fuels (e.g., metallic alloy, chloride), optimal device pin structures for liquefied fuel relocation, and nuclear and thermal-hydraulic characteristics of the device-loaded core under accident conditions to demonstrate the engineering applicability of the proposed device. This report discusses preliminary results regarding the nuclear requirements for inducing negative reactivity to achieve reactor shutdown under the expected device conditions during an accident.
防止快堆堆芯破坏事故的被动堆停装置的研制:初步研究
在2011年福岛核电站事故之后,考虑能够防止严重事故发生的措施对反应堆安全设计来说变得越来越重要。本文提出了一种新型的分组式无源反应堆停堆装置,扩大了钠冷快堆堆芯破坏事故预防策略的多样性和鲁棒性。所开发的装置包含带有燃料材料的引脚,该燃料材料在正常运行时处于固态,但当温度超过一定值时(即在潜在事故期间)会融化成液体。当发生无保护的流量损失(ULOF)或无保护的瞬时过功率(UTOP)事故时,该装置可以通过重力将液化装置燃料快速转移到引脚的下充气区,从而被动地提供显著的负反应性。即使发生ULOF或UTOP瞬态事件,在驱动燃料损坏之前,包含一些拟议装置的反应堆也会变成亚临界。本研究评估了用于装置燃料的候选材料(例如,金属合金、氯化物)、用于液化燃料重新安置的最佳装置销结构,以及事故条件下装置加载堆芯的核和热工特性,以证明拟议装置的工程适用性。本报告讨论了在事故期间在预期装置条件下诱导负反应性以实现反应堆关闭的核要求的初步结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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