高温氟化盐试验设施(FLUSTFA)的运行经验:发现的问题和前进的道路

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Sheng Zhang, Shuai Che, Adam Burak, Xiaodong Sun
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引用次数: 0

摘要

氟化盐冷却高温反应堆(FHR)是很有前途的第四代核反应堆,被动衰变热去除系统是其主要设计特征之一。我们设计并建造了一个高温氟化铝盐试验设施(FLUSTFA),用于进行整体效应试验(如验证按比例缩小的被动衰变热去除系统的设计)和单独效应试验(包括评估紧凑型热交换器的热液压性能)。FLUSTFA使用FLiNaK(LiF-NaF-KF:46.5-11.5-42 mol%)作为工作流体,在接近大气压的情况下工作温度可达700 °C。它由一个用于熔化和储存熔盐的储罐、一个模拟反应堆一级冷却剂系统的一级熔盐回路、一个代表被动衰变除热系统的二级熔盐回路、一个空气回路和一个冷却水回路组成,所有这些回路都通过热交换器进行热耦合。使用高温氮气和 FLiNaK 盐作为工作流体,进行了多次试运行测试。FLUSTFA 在 550-600 °C的初始运行期间发现了一些问题,如氟化氢的产生和泄漏、出现热量损失过大的局部热点、熔盐泵故障、超声波流量计读数异常以及充盐和回收管线堵塞。在解决所有这些问题的过程中,已经成功确定并实施了前进的道路。这些经验教训对于改进熔盐反应堆、聚变反应堆和下一代聚光太阳能发电站的高温熔盐系统的未来设计和建造非常有价值。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Operation experience of a high-temperature fluoride salt test facility (FLUSTFA): Issues identified and paths forward

Fluoride-salt-cooled High-temperature Reactors (FHRs) are promising Generation IV nuclear reactors, with a passive decay heat removal system serving as one of their key design features. A high-temperature FLUoride Salt Test FAcility (FLUSTFA) was designed and constructed to perform both integral-effect tests, such as validating the design of a scaled-down passive decay heat removal system, and separate-effect tests, including evaluating the thermal–hydraulic performance of compact heat exchangers. FLUSTFA utilizes FLiNaK (LiF-NaF-KF: 46.5–11.5–42 mol%) as the working fluid and operates up to 700 °C near the atmospheric pressure. It is comprised of a reservoir tank for melting and storing the salt, a primary molten salt loop that simulates the reactor primary coolant system, a secondary molten salt loop that represents the passive decay heat removal system, an air loop, and a chilled water loop, all of which are thermally coupled via heat exchangers. Several shakedown tests were carried out using high-temperature nitrogen and FLiNaK salt as the working fluid. A few issues were identified during initial operation of FLUSTFA at 550–600 °C, such as hydrogen fluoride generation and leakage, localized hot spots where excessive heat loss occurs, molten salt pump malfunctions, abnormal readings from ultrasonic flow meters, and blockage of salt charging and recycling lines. In addressing all these issues, paths forward have been successfully identified and implemented. The lessons learned are valuable in improving future design and construction of high-temperature molten salt systems for molten salt reactors, fusion reactors, and next-generation concentrated solar power plants.

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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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