A hybrid optimized Picard method for neutronic/thermal-hydraulic coupling problem

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-03-24 DOI:10.1016/j.anucene.2025.111380
Xinru Peng, Han Zhang, Lixun Liu, Qinrong Dou, Yingjie Wu, Jiong Guo, Fu Li
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Abstract

Picard iteration is a widely-used method for Neutronic/Thermal-Hydraulic (N/TH) coupling calculation in nuclear reactor, but it usually suffers from computational efficiency and stability, especially for complicated large-scale coupling issues. Residual balance method (RB) and Anderson acceleration method (AA) are two well-known optimized variants, where the former focusing on reducing the computational cost per outer iteration by adaptive tolerance, and the latter on decreasing the number of outer nonlinear iterations by using multiple iteration history information. However, combining these two methods causes incompatibility because the inaccurate function evaluations from the adaptive tolerance in the inner iterations disrupt the convergence rate of Anderson acceleration. In this work, a new hybrid optimized Picard iteration method (Picard-H) is proposed to combine the advantages of residual balance method and Anderson acceleration method by using an adaptive switching factor, avoiding the incompatibility from the inner iteration when approaching convergence. This new method could further enhance the efficiency of Anderson Acceleration, which could finish calculation much faster than both RB and Picard. A simplified neutronic k-eigenvalue problem in PWR with thermal–hydraulic feedback effect is utilized to evaluate the performance of the new optimized Picard method. The results demonstrate that for the simplified PWR model, the Picard-H method is 10% more computationally efficient than the AA method, more than twice as fast as the RB method, and more than four times faster than the traditional Picard method. In addition, the simple combination of RB and AA methods diverges due to the inexact fixed-point mapping function evaluation from the RB method. Furthermore, the hybrid method is robust against variations in parameters, such as the bounding parameter in the residual balance method and the memory depth in Anderson acceleration. The computational performance of the new method also is not sensitive to the choice of switching factor which is suggested to be adaptive when the residual drops to about 2 to 3 orders of magnitude of the initial residuals. The supplementary numerical results from the simplified HTR-10 model confirm that the Picard-H method exhibits 5% greater computational efficiency than the AA method and is over nine times faster than the traditional Picard method and the RB method.
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中子/热液耦合问题的混合优化皮卡尔法
皮卡德迭代是核反应堆中子/热工-水力(N/TH)耦合计算中广泛使用的一种方法,但其计算效率和稳定性存在一定的问题,特别是对于复杂的大规模耦合问题。残差平衡法(RB)和安德森加速法(AA)是两种著名的优化方法,前者侧重于利用自适应容差来减少每次外部迭代的计算成本,后者侧重于利用多个迭代历史信息来减少外部非线性迭代的次数。然而,将这两种方法结合使用会导致不兼容,因为在内部迭代中,从自适应容差得到的函数评估不准确,会影响安德森加速的收敛速度。本文通过引入自适应切换因子,结合剩余平衡法和安德森加速法的优点,提出了一种新的混合优化皮卡德迭代法(Picard- h),避免了逼近收敛时内部迭代的不兼容。这种新方法可以进一步提高安德森加速算法的效率,其计算速度比RB和Picard都快得多。利用一个具有热压-水力反馈效应的简化中子k-特征值问题对优化后的皮卡德方法进行了性能评价。结果表明,对于简化的PWR模型,Picard- h方法的计算效率比AA方法提高10%,比RB方法快2倍以上,比传统的Picard方法快4倍以上。此外,RB和AA方法的简单组合由于与RB方法不精确的不动点映射函数求值而产生分歧。此外,该方法对残差平衡法中的边界参数和安德森加速法中的记忆深度等参数的变化具有较强的鲁棒性。新方法的计算性能对切换因子的选择也不敏感,当残差下降到初始残差的2到3个数量级时,该方法可以自适应。简化HTR-10模型的补充数值结果证实,Picard- h方法的计算效率比AA方法提高5%,比传统的Picard方法和RB方法快9倍以上。
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
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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