Experimental investigation of the effect of operating conditions on internal flow behavior in APR1000

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yo Han Kim, Kihwan Kim, Hae-Seob Choi, Hyosung Seol, Byung-Jun Lim, Woo-Shik Kim, Dong-Jin Euh
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引用次数: 0

Abstract

Understanding the behavior of the primary coolant in a nuclear reactor is crucial for evaluating thermal margins and ensuring reactor safety. This study examines the behavior of the primary coolant using the ACOP experimental facility, a 1/5 scale model of the APR1000 reactor, to evaluate the effects of flow rate and flow unbalance on coolant distribution. Experiments were performed at flow rates of 60 %, 80 %, 100 %, and 110 % under balanced conditions, as well as under 15 % unbalanced and extreme unbalanced conditions with three pumps. The coolant flow characteristics were assessed by measuring the core inlet flow distribution, core outlet pressure, upper plenum pressure, and hot leg velocity using 177 core simulators. The results showed that the core inlet flow distribution ranged between 88 % and 112 % across all conditions. Under extreme unbalanced conditions, a maximum deviation of 5.3 % in single core flow distribution was observed. The outlet pressure distribution remained stable under four-pump conditions but showed greater variation with three pumps. The study concludes that coolant flow rate and flow unbalance had minimal impact under balanced four-pump conditions, while significant effects on outlet pressure, upper plenum pressure, and hot leg velocity were evident under extreme unbalanced conditions.
工况对APR1000内部流动特性影响的实验研究
了解核反应堆中主冷却剂的行为对于评估热裕度和确保反应堆安全至关重要。本研究利用ACOP实验设备(APR1000反应堆的1/5比例模型)研究了一次冷却剂的行为,以评估流量和流动不平衡对冷却剂分布的影响。实验分别在流量为60%、80%、100%和110%的平衡条件下进行,以及在15%不平衡和极端不平衡条件下使用三台泵进行。利用177台堆芯模拟器,通过测量堆芯入口流量分布、堆芯出口压力、上充气室压力和热支腿速度来评估冷却剂的流动特性。结果表明,在所有工况下,堆芯进口流量分布在88% ~ 112%之间。在极端不平衡条件下,单芯流分布的最大偏差为5.3%。出口压力分布在四泵条件下保持稳定,但在三泵条件下变化较大。研究表明,在平衡四泵工况下,冷却剂流量和流量不平衡对其影响最小,而在极端不平衡工况下,冷却剂流量和流量不平衡对出口压力、上腔压力和热腿速度的影响显著。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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