TREAT蒸汽包层氧化试验装置

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-10 DOI:10.1016/j.nucengdes.2025.114441

Musa A. Moussaoui, Klint S. Anderson, JunSoo Yoo, Nicolas E. Woolstenhulme

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引用次数: 0

摘要

为了在失冷剂事故（LOCA）环境下比较传统锆合金（Zry）包层与先进碳化硅（SiC）包层的化学降解，需要新的核试验能力。爱达荷国家实验室（INL）的瞬态反应堆测试（TREAT）设施自2017年重启以来，其瞬态燃料测试能力已经成熟。最新的实验架构是TREAT的瞬态水辐照系统（TWIST），该系统旨在支持轻水反应堆中耐事故燃料的鉴定。INL设计并分析了TWIST的自然循环蒸汽流改造，以产生包层氧化的原型条件。原位装置将通过电加热来驱动自然循环。此外，SiC包层需要加热到1700°C以上才能观察到失效，因此将使用带有辐射效应的内部原型核加热。热水力分析与RELAP5-3D（反应堆偏移和泄漏分析程序）估计蒸汽通量大于50 mg cm - 2 s - 1可以实现。这些助焊剂足以根据法规指南草案测试Zry包层，也足以根据过去的实验测试SiC包层。

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Device for steam cladding oxidation testing at TREAT

To compare the chemical degradation of conventional zirconium alloy (Zry) cladding to advance silicon carbide (SiC) cladding in a post loss of coolant accident (LOCA) environment, new nuclear testing capabilities are necessary. The Transient Reactor Test (TREAT) Facility at Idaho National Laboratory (INL) has matured its transient fuel testing capabilities since its 2017 restart. The most recent experiment architecture is the Transient Water Irradiation System in TREAT (TWIST), which is designed to support qualification of accident tolerant fuels in light water reactors. INL has designed and analyzed a natural circulation steam flow modification for TWIST to produce prototypic conditions of cladding oxidation. The in-situ device will be electrically heated to drive natural circulation. Moreover, the SiC cladding requires heating above 1700 °C to observe failure, thus internal prototypic nuclear heating with radiation effects will be used. Thermal hydraulic analysis with RELAP5-3D (Reactor Excursion and Leak Analysis Program) estimated steam fluxes greater than 50 mg cm⁻² s⁻¹ can be achieved. These fluxes are adequate to test Zry cladding according to draft regulatory guides and to test SiC cladding according to past experiments.

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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.