Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran
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Abstract

Abstract LOTUS reactor core is a small modular lead-cooled fast reactor with designed power of 200 MWth under development at VNU University of Science, Hanoi for a floating nuclear power plant application. For that purpose, advanced passive safety features and no refuelling requirement are the priorities in the core design process. To endure the continuous operation over a long lifetime, the start-up core exhibits excess reactivity to cover the reactivity loss due to burnup. The reactivity control system includes burnable poison and absorber rods and layers made of B4C which are employed in the reactor to minimize the excess reactivity of the core to about 1 $ to enhance the safety features of the core. The burnable poison is fixed inside the reactor while absorber rods/absorber layers were withdrawn or inserted in sequence to achieve the required excess reactivity of about 700 pcm. The reactivity control was arranged into ten steps to achieve the operating time of 15 effective full-power years without refuelling. Good neutronics behaviour of the core was observed with negative fuel temperature coefficient and coolant void reactivity and maximum radial power peaking factor of 1.32. However, a quite large residual absorption caused by fixed burnable poison inside fuel assemblies was revealed. In further study, to increase the neutron absorption efficiency of burnable poison in the fast spectrum as well as the reactor lifetime, a neutron moderator will be considered to add into the burnable poison rods.
碳化硼用于LOTUS小快堆反应性长期控制的可行性研究
摘要:LOTUS堆芯是一个小型模块化铅冷快堆,设计功率为200兆瓦,由河内VNU理工大学开发,用于浮动核电站。为此,先进的被动安全特性和无需换料是核心设计过程中的优先事项。为了承受长寿命的连续运行,启动堆芯表现出过度的反应性,以弥补燃耗造成的反应性损失。反应性控制系统包括由B4C制成的可燃毒物和吸收棒和层,用于反应堆中,将堆芯的过度反应性降至约1美元,以提高堆芯的安全性。可燃毒物被固定在反应器内,同时吸收棒/吸收层按顺序取出或插入,以达到所需的约700 pcm的过量反应性。反应性控制分为10个步骤,以实现15年有效满功率年的无换料运行时间。燃料温度系数为负,冷却剂空隙反应性为负,最大径向功率峰值因子为1.32,堆芯具有良好的中子性能。然而,燃料组件内的固定可燃毒物引起了相当大的残余吸收。在进一步的研究中,为了提高可燃毒物在快谱中的中子吸收效率和延长反应堆寿命,将考虑在可燃毒物棒中加入中子慢化剂。
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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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