NuScale US460螺旋盘管蒸汽发生器密度波振荡的方法学及验证性分析

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
P. Yarsky , J. Thompson , M. Bernard , J. Valverde
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引用次数: 0

摘要

在目前的工作中,开发了一个track - relap高级计算引擎(TRACE)模型来研究NuScale US460设计的螺旋线圈蒸汽发生器(HCSG)线圈中的密度波振荡(dwo)。NuScale US460设计包括一个整体的压水反应堆容器,利用自然循环提供正常的堆芯流动。热量通过一对缠绕在一起的hcsg从反应堆压力容器中排出。二次流在hcsg的盘管内沸腾并过热。在一定条件下,由于密度波不稳定机制,这些线圈中的流动可能变得不稳定。规范的目的是评估假定不稳定性的热载荷和水动力载荷,以确定这些载荷是否对线圈的完整性构成挑战。评估模型开发和评估过程(EMDAP)指导了模型开发工作。使用现象识别和排名表(PIRT)来确定与关键现象相关的知识和评估差距。为了支持TRACE分析螺旋线圈中dwo的适用性,进行了增量TRACE评估。作者考虑了dwo导致冷凝诱发水锤(CIWH)的可能性,并开发了一种使用TRACE保守估计CIWH超压负荷的方法。TRACE计算是在NuScale US460设计的启动范围内执行的,在该范围内可能发生不稳定的dwo。TRACE预测,启动过程中的某些操作条件会导致HCSG线圈中不稳定的dwo。对最严重的不稳定性进行进一步评估,以确定安全意义。结果表明,CIWH不太可能发生,热疲劳因素是可控的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Methodology and confirmatory analysis for density wave oscillation in NuScale US460 helical coil steam generators
In the current work, a TRAC-RELAP Advanced Computational Engine (TRACE) model was developed to study density wave oscillations (DWOs) in helical coil steam generator (HCSG) coils of the NuScale US460 design. The NuScale US460 design comprises an integral pressurized water reactor vessel that utilizes natural circulation to provide normal core flow. Heat is removed from the reactor pressure vessel by a pair of intertwined HCSGs. Secondary flow boils and becomes superheated inside the coils of the HCSGs. Under certain conditions, the flow in these coils may become unstable due to the density wave instability mechanism. The regulatory purpose is to evaluate the thermal and hydrodynamic loads of postulated instability to determine if these loads pose a challenge to the integrity of the coils. The Evaluation Model Development and Assessment Process (EMDAP) guided the model development effort. A Phenomena Identification and Ranking Table (PIRT) was used to determine knowledge and assessment gaps relative to key phenomena. Incremental TRACE assessment was performed to support the applicability of TRACE to analyze DWOs in helical coils. The authors considered the possibility of DWOs leading to condensation induced water hammer (CIWH) and developed an approach for conservatively estimating CIWH overpressure loads using TRACE. TRACE calculations were performed over the startup range of the NuScale US460 design where unstable DWOs could occur. TRACE predicted that certain operating conditions during startup would lead to unstable DWOs in the HCSG coils. The most severe instabilities were further evaluated to determine the safety significance. The results show that CIWH is unlikely to occur and that thermal fatigue considerations are manageable.
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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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