兆瓦级紧凑型热管堆堆芯设计方案研究

Study of Megawatt-class Compact Heat Pipe Reactor Core Conceptual Design

  • 摘要: 热管堆是利用热管导热元件的非能动导热特性来冷却堆芯的新型反应堆,兆瓦级紧凑型热管堆具有广泛的应用前景。本文提出并优化了一款高功率的紧凑型热管堆堆芯设计。利用开源蒙特卡罗软件OpenMC进行堆芯物理计算,通过比较反射能力与材料密度,采用氧化铍作为反射层。选用滑动反射层与控制棒作为反应性控制手段,反应性价值分别为6 705 pcm与7 698 pcm,反应堆总停堆深度超过10 000 pcm,且单个滑动反射层或安全棒卡住的情况下,堆芯能实现一定的停堆深度。为展平功率分布,燃料采用了三区分区布置方案,径向功率峰因子小于1.35。反应堆具有负的燃料多普勒反应性反馈,具有安全裕量。本文方案实现了堆芯的小型化,堆芯总重量小于2 t,满足15 a长寿命的运行需求。热力耦合计算结果表明本文方案满足基体与燃料温度限值要求。本文工作对高功率紧凑型热管堆系统的设计与优化具有一定的参考价值。

     

    Abstract: This study investigates the conceptual core design of a megawatt-class compact heat pipe reactor (HPR), targeting enhanced performance and safety for mobile and space-based applications. The reactor leverages the passive heat transfer capability of sodium heat pipes within a molybdenum-rhenium alloy matrix to achieve efficient cooling without active pumping systems, thereby significantly improving system compactness, reliability, and safety margins. The main objective is to propose a core design that minimizes size and weight, with a total core mass of less than 2 t and a volume of less than 1 m3, while ensuring long-term operation exceeding 15 a at a thermal power around 1 MW. The core physics calculations were conducted using the open-source Monte Carlo neutron transport code OpenMC, with nuclear data library JEFF3.3. Reflector material selection was systematically evaluated based on neutron reflection efficiency and material density, leading to the adoption of beryllium oxide as the primary reflector layer due to its favorable nuclear and thermo-mechanical properties in high-temperature environments. Radial fuel enrichment zoning was employed in a three-region layout (73%, 55%, and 19.75% 235U) to flatten the radial power distribution and reduce the power peak factor below 1.35, thereby mitigating fuel thermal stress risks. Reactivity control was achieved through a combination of sliding reflector layers composed of stainless steel and beryllium oxide, along with control rods featuring boron carbide and beryllium oxide neutron absorbers. These systems provide sufficient reactivity worth (6 705 pcm for sliding reflectors and 7 698 pcm for control rods) to enable effective shutdown and compensation during normal and transient operating states. Thermal-hydraulic performance was analyzed using finite element modeling in COMSOL, integrating the spatial power distributions from core physics to evaluate steady-state temperature fields. Results reveal maximum fuel temperatures remain below 1 543 K, satisfying design limits even when accounting for thermal expansion and corresponding porosity changes, with axial thermal expansion displacement exceeding radial expansion due to core geometry. Hot spots identified in the heat pipe gap regions exhibit temperature elevations approximately 40 K higher than adjacent fuel rods but remained within acceptable margins. Neutronic feedback calculations confirm the presence of inherently negative Doppler effects, contributing to natural safety characteristics of the design. Burnup simulations indicate the core maintains criticality with keff above 1 over the intended 15 a lifespan without control rod insertion, demonstrating strong fuel utilization and long-term operational feasibility. Thermal-mechanical coupling is essential for accurate peak temperature prediction, revealing a moderate increase compared to pure thermal analysis. The identified non-uniform power distribution (hot spots) in fuel rods near heat pipe interstices and the significant axial thermal expansion require specific engineering solutions in detailed design. This core design provides a valuable reference for developing high-power, transportable HPR systems.

     

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