分数标度分析方法在LSTF设施和压水堆上的应用

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
César Berna-Escriche , David Blanco , José Luis Muñoz-Cobo , Lucas Álvarez-Piñeiro , Alberto Escrivá
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引用次数: 0

摘要

缩放方法定量地评估小规模实验系统和全尺寸商业工厂在特定意外情景下的行为差异。这些方法指导实验设施的设计和操作,以可靠地复制大型系统,确保安全系统的开发和事故序列的准确预测。在实验设计阶段早期整合尺度计算,可以将结果可靠地外推到商业工厂。本研究应用分数标度分析(FSA)对热腿小断裂LOCA期间的LSTF实验设备和全尺寸西门子- kwu反应堆进行了比较(ROSA 1.2测试)。将瞬变过程划分为5个阶段,对每个阶段进行热-液相似性分析。尽管有轻微的尺度扭曲,但结果显示压力和液位演变具有很强的一致性,证实了该场景下设施之间具有良好的可扩展性。FSA展示了它的多功能性,允许从一种类型的设施(例如,西屋类型)的数据为不同类型的工厂(例如,西门子- kwu)的分析提供信息。一种新方法为整个瞬态提供了“标准化可扩展性”度量,压力和液位的优点值达到~ 0.3(远低于1),表明具有良好的可扩展性。非保守扭曲最小(<0.16),可以在工厂和瞬态之间进行定量比较,以增强安全性和设计验证。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Fractional Scaling Analysis - Methodology application to LSTF facility and a PWR for a small break LOCA transient
Scaling methodologies quantitatively assess the behavioral differences between small-scale experimental systems and full-size commercial plants during specific accidental scenarios. These methods guide the design and operation of experimental facilities to reliably replicate larger systems, ensuring safety systems are developed and accident sequences predicted accurately. Early integration of scaling calculations into the experimental design phase allows for reliable extrapolation of results to commercial plants. This study applied Fractional Scaling Analysis (FSA) to compare a scaled LSTF experimental facility and a full-size Siemens-KWU reactor during a Small Break LOCA in the hot leg (ROSA 1.2 test). The transient was divided into five phases, each analyzed for thermal-hydraulic similarity. Despite minor scaling distortions, the results showed strong consistency in pressure and level evolution, confirming good scalability between the facilities for this scenario. FSA demonstrated its versatility, allowing data from one type of facility (e.g., Westinghouse-type) to inform analyses for plants of a different type (e.g., Siemens-KWU). A new method provided a "normalized scalability" metric for the entire transient, with figures of merit for pressure and level reaching ∼0.3 (far below 1), indicating good scalability. Non-conservative distortions were minimal (<0.16), enabling quantitative comparisons across plants and transients for enhanced safety and design validation.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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