LOTUS反应堆动态展开过程的中子与热工耦合分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-23 DOI:10.1016/j.nucengdes.2024.113798
Yantao Luo , Tian Zhang , Antonio Cammi , Xiang Wang
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引用次数: 0

摘要

普通的池式加热堆设计存在一定的安全隐患,特别是在地震等自然灾害中。在这种情况下,如果池水泄漏,反应堆堆芯很可能暴露在空气中,这可能导致堆芯熔毁。所提出的可扩展LOTUS反应堆为这个问题提供了一个解决方案。它的堆芯可以在重力和浮力的作用下展开,在事故发生时被动关闭反应堆,排出堆芯热量。在展开过程中,堆芯的几何屈曲和材料屈曲都发生非线性变化,这是核工程领域尚未讨论的新问题。因此,通过数值模拟,LOTUS反应堆的出现需要一个全新的、复杂的核-热瞬态耦合过程。我们使用SERPENT和STAR-CCM +进行了单物理场和核-热耦合计算。前者提供了一个快速、低维的计算,作为耦合计算的参考。功率、有效乘数和温度的变化表明,展开运动可以迫使反应堆关闭,剩余池水有效降低堆芯温度。对于耦合计算,首先通过验证计算确认了耦合策略的正确性和稳定性。然后采用Picard迭代法进行稳态耦合计算,迭代207次后得到收敛。在展开运动开始时,单物理场计算与耦合计算的最大功率差可达6%。这种差异随着时间的推移逐渐减小,当展开角达到0.6°时消失。与单物理计算相比,耦合计算得到的温度非均匀分布更符合实际分布。这些差异突出了耦合计算的必要性和重要性。
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Neutronic and thermal-hydraulic coupling analysis of the dynamic unfolding process of the LOTUS reactor
Common pool-type heating reactor designs have certain safety risks, particularly during natural disasters such as earthquakes. In such scenarios, if the pool water leaks, the reactor core is likely exposed to air, which can cause core meltdown. The proposed expandable LOTUS reactor offers a solution to this problem. Its core can unfold under the influence of gravity and buoyancy, passively shut down the reactor and remove the core heat when accidents occur. During the unfolding process, both geometric buckling and material buckling of the core change non-linearly, and this is a new problem for nuclear engineering that was not discussed yet. Therefore, the emergence of the LOTUS reactor entails an entirely new and intricate nuclear-thermal transient coupling process through numerical simulation. We used SERPENT and STAR-CCM + to conduct single-physical-field and nuclear-thermal coupling calculations. The former provides a fast, low-dimensional calculation that serves as references for the coupling calculation. The changes in power, effective multiplication factor and temperature indicate that the unfolding motion can force the reactor to shut down, and the remaining pool water effectively decreases the core temperature. For the coupling calculations, first, validation calculations confirmed the correctness and stability of the coupling strategy. Then, steady-state coupling calculations were conducted using Picard iteration method and converged after 207 iterations. There was a maximal power difference of up to 6 % between single-physical-field calculations and coupling calculations at the beginning of the unfolding motion. This difference gradually decreased over time and disappeared when the unfolding angle reached 0.6°. Compared to the single-physical calculations, the non-uniformly distributed temperature obtained from the coupling calculations was more consistent with the actual distribution. These differences highlight the necessity and importance of coupling calculations.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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