Failure investigation and mitigation after experimental research reactor fuel plate deformation in an irradiation device

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-27 DOI:10.1016/j.nucengdes.2024.113796
B. Rossaert , C. Bojanowski , A. Leenaers , G. Cornelis , E. Feldman , E. Wilson , S.Van Dyck , J. Stevens , J. Wight
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Abstract

Experimental research reactor fuel testing is conducted in the Belgian Reactor 2 (BR2) of the Belgian Nuclear Research Centre (SCK CEN) in dedicated irradiation vehicles or rigs. One such vehicle allows flat full-size fuel plates to be irradiated by inserting them into slotted baskets that captures a narrow portion of the longitudinal edges of the plates. The motion of the fuel plates within the baskets is possible within the narrow slots and thus, the plate is considered to be unattached. The design intentionally omits fixing mechanisms of the fuel plates to the baskets to facilitate the inspection and repositioning of the plates between the irradiation cycles and the accommodation of thermal expansion of the plates in the lateral direction. However, loosely inserted fuel plates have weak structural boundary conditions allowing for larger out-of-plane deflections caused by hydrodynamic loads exerted by the flowing coolant, as compared to those of fixed plates. Unexpected large deformations of plates occurred in several irradiation cycles that further resulted in a loss of cladding integrity. These deformations could not be attributed to a single source. This triggered a series of thermal hydraulic, structural, and fluid–structure interaction analyses aiming at understanding the observed phenomenon. The analyses revealed that, for a certain combination of unfavorable manufacturing and assembly tolerances, fuel plate edges could escape out of the slots in the irradiation basket due to the hydrodynamic load. Subsequently, the plate could become wedged inside the basket coolant channel opening. This resulted in reduced coolant flow and accelerated temperature increase and thermal expansion of the plate while under irradiation. This unfavorable feedback loop could then lead to excessive plate surface temperatures, deformed plates and cladding failure, as was observed in the experiments. These analyses not only provided a probable cause of the fuel plate failures, but also resulted in a new and improved design of the irradiation basket to avoid these issues in the future. A series of recent successful irradiations confirm that the sources of failures were identified correctly, and the implemented mitigations were adequate.
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辐照装置试验研究堆燃料板变形后的失效调查与缓解
实验研究反应堆燃料测试是在比利时核研究中心(SCK CEN)的比利时2号反应堆(BR2)的专用辐照车辆或钻机中进行的。一种这样的车辆允许将全尺寸的平板燃料板插入有槽的筐中进行辐照,该筐捕获了平板纵向边缘的狭窄部分。燃料板在篮内的运动在窄槽内是可能的,因此,该板被认为是独立的。设计故意省略了燃料板在篮上的固定机构,以便于在辐照循环之间检查和重新定位燃料板,并适应燃料板在侧向的热膨胀。然而,与固定板相比,松散插入的燃料板具有较弱的结构边界条件,允许由流动冷却剂施加的流体动力载荷引起的较大的面外挠度。在几个辐照循环中,钢板发生了意想不到的大变形,进一步导致包层完整性的损失。这些变形不能归因于一个单一的来源。这引发了一系列旨在理解所观察到的现象的热工、构造和流固耦合分析。分析表明,在一定的制造和装配公差组合条件下,由于水动力载荷的作用,燃料板边缘可能会从辐照篮槽中逸出。随后,板可能楔入篮内的冷却剂通道开口。这导致冷却剂流量减少,加速了板在辐照下的温度升高和热膨胀。这种不利的反馈回路可能导致过高的板表面温度,变形板和包层失效,如在实验中观察到的。这些分析不仅提供了燃料板失效的可能原因,而且还导致了一种新的和改进的辐照篮设计,以避免未来发生这些问题。最近一系列成功的辐照证实,已正确地确定了故障的来源,所实施的缓解措施是充分的。
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
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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