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熔盐球床堆径向流堆芯的热工水力分析

Thermal-Hydraulics Analyses of Radial Flow Core of Molten Salt Pebble-Bed Reactor

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【作者】 薛春辉董玉杰

【Author】 Xue Chunhui;Dong Yujie;Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Institute of Nuclear and New Energy Technology,Tsinghua University;

【机构】 清华大学核能与新能源技术研究院先进反应堆工程与安全教育部重点实验室

【摘要】 核热泉(NHS)堆是一种新型熔盐球床概念设计堆,其冷却剂径向流过堆芯,具有满功率自然循环特性。基于多孔介质局部非热平衡模型,利用计算流体力学(CFD)通用软件Fluent计算核热泉堆径向流堆芯的热工水力特性,并比较了不同的内、外孔板开孔率的影响。结果表明,内孔板开孔率对冷却剂流量分布影响较大;燃料中心温度具有相当的安全裕量,冷却剂横向流过堆芯的阻力远低于浮升力,能够实现全回路的自然循环。

【Abstract】 Nuclear Hot Spring is a novel design concept of molten salt pebble-bed reactor, featured by the full power natural circulation, with the primary coolant flowing radially through the reactor core. By using CFD software Fluent, the thermal-hydraulics of the radial flow reactor core of the NHS were obtained based on the local thermal non-equilibrium(LTNE) porous media model. Different opening ratios of the central and outer perforated plate were simulated. The simulation results indicated that the opening ratio of the central perforated plate has a great effect on the flow field distribution of the coolant; the maximum pebble center temperatures are far below the safety limit of the fuel, the core resistance is considerably less than the buoyant force, indicating that the natural circulation under full power operation is possible.

【关键词】 CFD多孔介质熔盐球床堆
【Key words】 CFDPorous mediaMolten salt pebble-bed reactor
【基金】 国家科技重大专项资助项目(ZX069)
  • 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2018年01期
  • 【分类号】TL33
  • 【下载频次】126
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