Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor with SiC Matrix and TRISO Particle Fuel

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Zhang Tao, Shanfang Huang
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引用次数: 0

Abstract

Additive manufacturing (AM) is a transformational digital manufacturing technology featured with rapidity, customizability, precision, and economy, which is fundamentally altering the way components are designed and manufactured. AM enables the freedom of design, and makes full use of complexity of geometry which "comes for free". Applying AM technology to nuclear industry can yield advanced reactor designs with function and structure matched for the best thermal, fluidic and mechanical performance. In this work, an AM-informed reactor core design with SiC matrix and TRISO particle fuel is proposed and analyzed. The core is an integrated 3D-printed SiC bulk with helical cruciform coolant channels, and the UO2-TRISO fuel particles are dispersed in the bulk. A multi-physics analysis framework for irregular geometry is developed to analyze and further optimize the reactor design. The TRISO particle positions are generated with discrete element method. The Reactor Monte Carlo code (RMC) and the CFD software STAR-CCM+ are used for the neutronic and thermal-fluidic analyses, respectively. RMC simulates the neutron transport to predict the effective multiplication factor and power distribution. STAR-CCM+ calculates the flow and heat transfer in coolant channels and heat conduction in solid matrix with the power distribution as the heat source. The results show that the power peaking factor FQ decreases below 1.65, the heat transfer area increases by 30.3% and the fuel peaking temperature decreases by 25 K. The optimized AM-informed design enjoys better neutronic and thermal-fluidic performance than those with regular geometry.
SiC基质和TRISO颗粒燃料添加剂反应器的中子和热流体分析
增材制造(AM)是一种变革性的数字制造技术,具有快速、可定制、精确和经济的特点,从根本上改变了零部件的设计和制造方式。增材制造实现了设计的自由,并充分利用了“免费”的几何复杂性。将增材制造技术应用于核工业,可以产生功能和结构相匹配的先进反应堆设计,以获得最佳的热、流、力学性能。在这项工作中,提出并分析了一种基于am的SiC基质和TRISO颗粒燃料反应堆堆芯设计。核心是一个集成的3d打印SiC块体,具有螺旋十字形冷却剂通道,UO2-TRISO燃料颗粒分散在块体中。为了分析和进一步优化反应堆设计,开发了不规则几何的多物理场分析框架。采用离散元法生成三iso粒子位置。中子和热流体分析分别使用反应器蒙特卡罗代码(RMC)和计算流体动力学软件STAR-CCM+。RMC模拟中子输运来预测有效倍增系数和功率分布。STAR-CCM+以功率分布为热源,计算冷却剂通道内的流动和传热以及固体基质中的热传导。结果表明:功率峰值因数FQ降至1.65以下,换热面积增加30.3%,燃油峰值温度降低25 K;优化后的AM-informed设计比常规几何形状的设计具有更好的中子和热流体性能。
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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