Helical coil steam generator stability experiments with the MOTEL test facility

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-09-07 DOI:10.1016/j.nucengdes.2024.113566

Vesa Riikonen , Joonas Telkkä , Virpi Kouhia , Markku Puustinen , Giteshkumar Patel , Lauri Pyy , Antti Räsänen , Eetu Kotro , Juhani Hyvärinen , Afeef Murad

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Abstract

Small modular reactors (SMRs) are under extensive development globally. Some SMR concepts have design features that are rare in traditional pressurized water reactors (PWRs). One such feature is a helical coil steam generator which differs from traditional horizontal and vertical inverted U-tube steam generators in several ways. The helical coil steam generator is a once-through design where the primary side flow runs in the shell side and the secondary side flow runs inside the tubes and can generate superheated steam. Boiling instabilities in helically coiled tubes are a crucial research question due to their potentially negative impact on steady plant operation. The MOTEL (MOdular TEst Loop) facility at LUT University is a model of an integral SMR with a helical coil steam generator representing an integral pressurized water reactor. A large variation of core power and feedwater flow values were tested to map MOTEL operating conditions in which the steam production in the helical coil steam generator is stable.

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利用 MOTEL 试验设备进行螺旋线圈蒸汽发生器稳定性试验

全球正在广泛开发小型模块化反应堆（SMR）。一些小型模块化反应堆概念具有传统压水反应堆（PWR）少有的设计特点。螺旋盘管蒸汽发生器就是其中之一，它与传统的水平和垂直倒 U 型管蒸汽发生器有多处不同。螺旋盘管蒸汽发生器采用一次通过式设计，一次侧气流在壳侧流动，二次侧气流在管内流动，可以产生过热蒸汽。螺旋盘管中的沸腾不稳定性是一个关键的研究问题，因为它可能会对设备的稳定运行产生负面影响。LUT 大学的 MOTEL（MODular TEst Loop）设施是一个整体式 SMR 模型，其螺旋盘管蒸汽发生器代表了一个整体式压水堆。我们测试了大量不同的堆芯功率和给水流量值，以绘制出螺旋线圈蒸汽发生器蒸汽产量稳定的 MOTEL 运行条件图。

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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.