Research on burnup solution method based on adaptive time step size

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-05-17 DOI:10.1016/j.nucengdes.2025.114152

Cong Zhang , Ling Chen , Yongfa Zhang , Song Li , Binhang Zhang

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引用次数: 0

Abstract

The time step size directly affects the accuracy and efficiency of burnup calculation. The division of the burnup step size depends on empirical knowledge, lacking a definitive theoretical foundation. In order to balance the influence of step size on calculation accuracy and efficiency, a burnup solution method based on adaptive time step size is developed in this work. In this research, the feasibility of the fast burnup solution method, which can solve the nucleon density at different burnup times using the same burnup matrix, based on the Mini-Max Polynomial Approximation (MMPA) is verified both theoretically and numerically. On this basis, a theoretical model for the division of burnup time step size is established based on the conversion relation between thermal power and neutron flux. Optimal step size is determined by iterative calculation to minimize the influence of the assumption of constant neutronics parameters on the calculation accuracy in the current time step and realize the adaptive discretization of the burnup step size during the whole life of the reactor. Furthermore, combined with the semi-predictor–corrector coupling strategy, an adaptive burnup step coupling strategy based on the MMPA method is proposed. Finally, the MOX fuel pin-cell and BWR assembly benchmarks are used for verification. The calculated results agree with the reference values, proving the correctness and effectiveness of the adaptive time step size method for solving burnup equations based on MMPA. This work provides a theoretical basis for the division of burnup time step size.

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基于自适应时间步长的燃耗求解方法研究

时间步长直接影响燃耗计算的准确性和效率。燃耗步长的划分依赖于经验知识，缺乏明确的理论基础。为了平衡步长对计算精度和效率的影响，本文提出了一种基于自适应时间步长的燃耗求解方法。本研究从理论上和数值上验证了基于最小最大多项式近似（Mini-Max Polynomial Approximation， MMPA）的快速燃耗求解方法的可行性，该方法可以利用相同的燃耗矩阵求解不同燃耗时间下的核子密度。在此基础上，基于热功率与中子通量的换算关系，建立了燃耗时间步长划分的理论模型。通过迭代计算确定最优步长，使中子参数恒定假设对当前时间步长计算精度的影响最小，实现反应堆全寿命燃耗步长的自适应离散化。在此基础上，结合半预测-校正耦合策略，提出了基于MMPA方法的自适应燃耗阶跃耦合策略。最后，使用MOX燃料针式电池和沸水堆组件基准进行验证。计算结果与参考值吻合，证明了基于MMPA的自适应时间步长法求解燃耗方程的正确性和有效性。该工作为燃耗时间步长划分提供了理论依据。

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

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.