Integrated multiphysics assessment of grid-to-rod fretting mitigation: enhancing nuclear safety through improved fuel integrity

IF 2.5 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Nuclear Engineering and Design Pub Date : 2026-04-01 Epub Date: 2026-01-12 DOI:10.1016/j.nucengdes.2025.114696
Quazi Md. Zobaer Shah , Md Mahabub Hasan Mousum , Debashis Datta , Md. Arefin Kowser , Mohammad Asaduzzaman Chowdhury , Md. Shojib Mia , Shahpara Sheikh Dola
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引用次数: 0

Abstract

Grid-to-rod fretting (GTRF) represents a persistent challenge to the mechanical integrity and service life of nuclear fuel assemblies across various reactor technologies. As a leading cause of fuel failures in pressurized water reactors and a growing concern in other light water reactor systems, GTRF has drawn significant attention from both experimental and computational communities. Recent investigations have expanded in scope and precision, with advances in multiphysics simulation frameworks, in-reactor diagnostics, and surface-engineered cladding materials. These studies have illuminated complex dependencies on flow turbulence, spacer grid geometry, contact dynamics, and material behavior under irradiation, yet several technical uncertainties continue to limit predictive confidence. This work presents a comprehensive synthesis of developments surrounding GTRF, highlighting current approaches that span high-resolution fluid-structure interaction modeling, fretting-wear characterization, and emerging mitigation strategies. Specific phenomena such as fretting wear response under variable coolant conditions, coating-induced changes in contact fatigue, and the evolving mechanical role of spacer supports are examined through a multidisciplinary lens. While no single mechanism dominates across all contexts, the convergence of insights from structural mechanics, tribology, and reactor operation points toward integrated pathways for addressing the problem. GTRF arises from tightly coupled turbulent forcing, nonlinear rod-support dynamics and evolving material states. Integrated LES→FSI→wear pipelines, validated against autoclave and flow-loop experiments, offer the most promising path toward predictive life-assessment. It was recommended that coordinated high-burnup testing, open benchmark datasets, and development of reduced-order multiphysics tools with uncertainty quantification to enable quantified life-predictions for advanced claddings and higher-burnup operation. Viewing GTRF as a systems-level challenge highlights its implications for fuel reliability and safety and underscores the need for focused research to achieve quantitative, licensing-grade predictions.
电网到棒微动缓解的综合多物理场评估:通过提高燃料完整性加强核安全
网格-棒微动(GTRF)是对各种反应堆技术中核燃料组件的机械完整性和使用寿命的持续挑战。作为压水堆燃料失效的主要原因和其他轻水堆系统日益受到关注,GTRF引起了实验界和计算界的极大关注。随着多物理场模拟框架、反应堆内诊断和表面工程包层材料的进步,最近的研究在范围和精度上都有所扩大。这些研究揭示了流动湍流、间隔网格几何形状、接触动力学和辐照下材料行为的复杂依赖关系,但一些技术上的不确定性继续限制了预测的可信度。这项工作介绍了围绕GTRF的全面综合发展,重点介绍了目前跨越高分辨率流固耦合建模、微动磨损表征和新兴缓解策略的方法。通过多学科的视角,研究了不同冷却剂条件下的微动磨损响应、涂层引起的接触疲劳变化以及垫片支撑的机械作用演变等具体现象。虽然没有单一的机制在所有情况下都占主导地位,但从结构力学、摩擦学和反应堆操作方面的见解的融合指向了解决问题的综合途径。GTRF是由紧密耦合的湍流强迫、非线性杆支撑动力学和不断变化的材料状态引起的。集成LES→FSI→磨损管道,通过高压灭菌器和流动回路实验验证,为预测寿命评估提供了最有希望的途径。建议协调高燃耗测试,开放基准数据集,开发具有不确定性量化的降阶多物理场工具,以实现高级包层和高燃耗操作的量化寿命预测。将GTRF视为系统层面的挑战,凸显了其对燃料可靠性和安全性的影响,并强调了集中研究以实现定量、许可级预测的必要性。
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来源期刊
Nuclear Engineering and Design
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.
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