lbe冷却快堆BLESS-D燃料管理策略

IF 0.4 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Fuel Cycle and Waste Technology Pub Date : 2022-08-08 DOI:10.1115/icone29-90443
Zhen Luo, Eing Yee Yeoh, Xiaosong Chen, Linsen Li, Mian Xing
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引用次数: 0

摘要

作为第四代国际论坛(GIF)选定的六个候选核反应堆之一,铅冷快堆(LFR)已成为最具发展前景的概念之一,受到了各研究所的广泛关注。中国国家电力投资集团研究院提出了一种铅铋共晶(LBE)冷却快堆——bliss - d。燃料管理是反应堆设计的关键,因为它影响反应堆的经济性。尽管对压水堆燃料管理的研究已经成熟,但对轻堆燃料管理的研究还很少。燃料管理设计包括从初始循环到过渡循环,再到平衡循环的全过程。为了获得更好的加注方案和优化平衡循环的关键参数,首先提出了一种新的加注方案,而传统的加注模拟是逐周期进行的,需要消耗大量的计算资源。如果方案未能达到预期,则支出将成倍增加,直到修改后的方案达到安全设计标准。本文采用“拟平衡循环”方法代替传统方法进行燃料管理设计。“拟平衡循环”方法通过用初始堆芯布置和换料方案估计的近似核素密度代替燃料模型,直接求解堆芯平衡循环的关键参数。本文提出了一种采用“伪平衡循环”方法的两批换料方案,并设计了过渡循环,以保证新鲜堆芯顺利过渡到“伪平衡循环”状态的可行性。结果表明,当燃耗计算到第5个循环时,反应堆的装配峰值因子、线性功率密度、延迟中子分数、提示中子寿命等关键参数与“伪平衡循环”基本吻合,证明了“伪平衡循环”方法可以准确、高效地用于换料方案设计。
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Fuel Management Strategy of LBE-Cooled Fast Reactor BLESS-D
As one of the six nuclear reactor candidates selected by the Generation IV International Forum (GIF), lead-cooled fast reactor (LFR) has become one of the most promising concepts and attracted more attention from the institutes. A lead-bismuth eutectic (LBE) cooled fast reactor called BLESS-D has been proposed by State Power Investment Corporation Research Institute of China. The fuel management is critical to reactor design because it affects reactor economics. Although the research on fuel management of PWR has matured, there are few studies on fuel management for LFR. Fuel management design includes the entire process from initial cycle to transition cycle, and to equilibrium cycle. To obtain a better refueling scheme and optimize the key parameters of equilibrium cycle, a new refueling scheme is first proposed, and then traditionally, the simulation covering the entire refueling operation is required cycle by cycle, resulting in consuming a massive computing resource. If the scheme fails to meet expectations, expenditure will multiply until the modified scheme meets the safety design criteria. Fuel management design using “pseudo-equilibrium cycle” instead of traditional method is carried out in this work. The “pseudo-equilibrium cycle” method can directly solve the core key parameters of equilibrium cycle by replacing fuel model with approximate nuclides densities estimated from initial core arrangement and refueling scheme. In this paper, a two-batch refueling scheme is proposed with “pseudo-equilibrium cycle” method and then transition cycle are designed to ensure the feasibility that the fresh core successfully transition to the “pseudo-equilibrium cycle” state. Afterwards, neutronics parameters are solved for each cycle from the fresh core and results show that when the burnup calculation comes to the 5th cycle, the reactor key parameters, including assembly peaking factor, linear power density, delayed neutron fraction, and prompt neutron lifetime are in good agreement with “pseudo-equilibrium cycle”, which proves that the “pseudo-equilibrium cycle” method can be used accurately and efficiently to design the refueling scheme.
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来源期刊
CiteScore
0.80
自引率
25.00%
发文量
35
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