The scaling technology in nuclear reactor thermal hydraulic

Wang L. S.; Yan B. H.

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The scaling technology in nuclear reactor thermal hydraulic

机译：核反应堆热液中的缩放技术

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Scaling is an important issue in nuclear reactor safety analysis. Due to the safety relevance and cost, it is a big challenge for the scientists to design and construct experimental facilities capable of simulating the performance of nuclear reactor systems. Several approaches have been developed to address the scaling issue, including non-dimensional analysis of conservative equations, derivation and application of scaling factors, etc. In this work, the key areas and approaches for scaling technology in nuclear reactor thermal hydraulic are systematically analyzed and summarized. Some valuable conclusions and suggestions for future work are proposed. (C) 2021 Elsevier Ltd. All rights reserved.

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《Annals of nuclear energy》 |2021年第10期|108440.1-108440.15|共15页
作者
Wang L. S.; Yan B. H.;
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作者单位

Sun Yat Sen Univ Sino French Inst Nucl Engn & Technol Zhuhai Peoples R China;

Sun Yat Sen Univ Sino French Inst Nucl Engn & Technol Zhuhai Peoples R China;

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原文格式 PDF
正文语种 eng
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关键词
Scaling method; Distortion; Thermal hydraulic; Critical heat flux;

机译：缩放方法;失真;热液压;临界热通量;

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专利

1. The Dynamic-Implicit-Additional-Source (DIAS) method for multi-scale coupling of thermal-hydraulic codes to enhance the prediction of mass and heat transfer in the nuclear reactor pressure VESSEL [J] . Kanglong Zhang, Victor Hugo Sanchez-Espinoza International Journal of Heat and Mass Transfer . 2020,第Feba期

机译：动态-附加-源（DIAS）方法用于热工代码的多尺度耦合，以增强对核反应堆压力VESSEL中质量和热传递的预测
2. Scaling in nuclear reactor system thermal-hydraulics [J] . F.DAuria, G.M. Galassi Nuclear Engineering and Design . 2010,第10期

机译：核反应堆系统热工水力缩放
3. Thermal-Hydraulics, Physical Chemistry, and Technology at Nuclear Power Stations Equipped with Fast-Neutron Sodium-Cooled Reactors [J] . V. V. Alekseev, A. D. Efanov, F. A. Kozlov, Thermal engineering . 2007,第12期

机译：配备快中子钠冷反应堆的核电站的热工，物理化学和技术
4. Development of Predictable Technology for Thermal/Hydraulic Performance of Reduced-Moderation Water Reactors (2) - Large-scale Thermal/Hydraulic Test and Model Experiments [C] . Masatoshi KURETA, Wei LIU, Hidesada TAMAI, International Congress on Advances in Nuclear Power Plants . 2004

机译：减压水反应器热/水力性能的可预测技术的开发（2） - 大规模热/液压试验和模型实验
5. Scaling approach and thermal-hydraulic analysis in the reactor cavity cooling system of a high temperature gas -cooled reactor and thermal-jet mixing in a sodium fast reactor. [D] . Omotowa, Olumuyiwa A. 2014

机译：高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析，以及钠快速反应堆中的热喷射混合。
6. Successful hydraulic strategies to start up OLAND sequencing batch reactors at lab scale [O] . Thomas Schaubroeck, Samik Bagchi, Haydée De Clippeleir, 2012

机译：成功的水力策略可在实验室规模启动OLAND顺序批处理反应器
7. Figure 2 from: Doan TZC, Lazarenko GE, Lazarenko DG (2019) Calculations of research reactor thermal hydraulics based on VVER-440 fuel assamblies. Nuclear Energy and Technology 5(4): 317-321. https://doi.org/10.3897/nucet.5.48397 [O] . Thi Zieu Chang Doan, Georgy E. Lazarenko, Denis G. Lazarenko 2019

机译：图2来自：Doan TZC，Lazarenko GE，Lazarenko DG（2019）基于VVER-440燃料assamblies的研究反应器热水力学计算。核能和技术5（4）：317-321。 https://doi.org/10.3897/nucet.5.48397
8. Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Held at Saratoga Springs, New York on October 5-8, 1980. Volume 1. PWR and BWR Reactor-Plant Performance Analysis and Containment Technology [R] . Rippel, R. R. 1980

机译：aNs / asmE / NRC核反应堆热工水力国际专题会议论文集于1980年10月5日至8日在纽约萨拉托加斯普林斯举行。第1卷。压水堆和BWR反应堆 - 工厂性能分析和遏制技术

The scaling technology in nuclear reactor thermal hydraulic

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