高级检索

微型铅冷快堆堆芯控制策略设计及源项分析

Core Control Strategy Design and Source Term Analysis of Miniature Lead-cooled Fast Reactor

  • 摘要: 为应对微型铅冷快堆在紧凑尺寸和高泄漏环境下,传统插入式控制棒难以应用的挑战,本工作旨在设计并评估一套新型反应性控制策略,并对停堆后的源项进行系统分析,以确保其运行安全并为后续工程设计提供依据。本工作提出了一种由主动控制鼓(调节鼓与安全鼓)和非能动安全块组成的多级冗余反应性控制策略。该策略的创新性在于:利用堆外控制鼓实现对堆芯扰动小的精细调节与停堆,并引入基于浮力驱动的非能动安全块作为纵深防御的最终保障。研究采用蒙特卡罗程序对该控制系统的反应性价值进行三维精确建模,并结合ORIGEN2程序对分区布置的燃料组件进行10 a的停堆源项演化计算,保证了计算的物理一致性。计算结果表明控制策略具备充足的停堆裕量,在最保守工况下,控制鼓协同作用可使堆芯达到深度次临界;非能动安全块能在主动系统失效时确保安全停堆,显著提升了系统的固有安全性。源项分析明确了不同冷却阶段的主要贡献核素,得到了分区组件放射性活度、衰变热、中子源和γ源等关键信息。本工作所设计的创新性多级冗余控制策略,能够有效、可靠地实现微型铅冷快堆的反应性控制与安全停堆。本研究获得的乏燃料详细源项特性,特别是对不同冷却阶段和能量区间内关键贡献核素的精准识别,为相关堆型的屏蔽设计、乏燃料管理和安全评价提供了关键的物理依据和数据基础。

     

    Abstract: Miniature Lead-Cooled Fast Reactors (LFRs) pose a substantial challenge to traditional reactivity control methods due to their compact core size and high neutron leakage environment, which render traditional insertable control rods ineffective. This study introduces the design and evaluation of a novel reactivity control strategy, coupled with a systematic source term analysis post-shutdown, to ensure operational safety and provide a robust foundation for future engineering. We propose an innovative, multi-layered redundant control strategy that includes active control drums (for regulation and safety) and passive safety blocks. This approach uniquely integrates ex-core control drums for fine-tuned, low-perturbation reactivity management and shutdown, with buoyancy-driven passive safety blocks serving as the ultimate defense-in-depth mechanism. The reactivity worth of this system was accurately modeled in three dimensions using a Monte Carlo code, while the source term evolution over a ten-year post-shutdown period was calculated for zoned fuel assemblies using the ORIGEN2 code, ensuring physical consistency. The results indicate that the proposed control strategy maintains an ample shutdown margin, achieving a deep subcritical state through the synergistic operation of all control drums, even under the most conservative accident scenarios. Moreover, the passive safety blocks guarantee a shutdown in the event of an active system failure, significantly enhancing the reactor's inherent safety. The source term analysis identifies the primary contributing nuclides at various cooling stages and provides essential data on zonal component activity, decay heat, and neutron and gamma source strengths. In conclusion, the innovative control strategy developed in this study enables effective and reliable reactivity control and safe shutdown for miniature LFRs. Furthermore, this work characterizes the spent fuel source term in detail, accurately identifying key contributing nuclides across various cooling stages and energy intervals. These findings provide a crucial physical basis and comprehensive data support for shielding design, spent fuel management, and safety evaluation.

     

/

返回文章
返回