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Experimental Characterization of Leak Detection Systems in HLM Pool Using LIFUS5/Mod3 Facility
Nuclear Technology ( IF 1.5 ) Pub Date : 2020-06-30 , DOI: 10.1080/00295450.2020.1749480
Marica Eboli 1 , Alessandro Del Nevo 1 , Nicola Forgione 2 , Fabio Giannetti 3 , Daniele Mazzi 4 , Marco Ramacciotti 5
Affiliation  

Abstract In the framework of the European Union MAXSIMA project, the safety of the steam generator (SG) adopted in the primary loop of the Heavy Liquid Metal Fast Reactor has been studied investigating the consequences and damage propagation of a SG tube rupture event and characterizing leak rates from typical cracks. Instrumentation able to promptly detect the presence of a crack in the SG tubes may be used to prevent its further propagation, which would lead to a full rupture of the tube. Application of the leak-before-break concept is relevant for improving the safety of a reactor system and decreasing the probability of a pipe break event. In this framework, a new experimental campaign (Test Series C) has been carried out in the LIFUS5/Mod3 facility, installed at ENEA Centro Ricerche Brasimone, in order to characterize and to correlate the leak rate through typical cracks occurring in the pressurized tubes with signals detected by proper transducers. Test C1.3_60 was executed injecting water at about 20 bars and 200°C into lead-bismuth eutectic alloy. The injection was performed through a laser microholed plate 60 μm in diameter. Analysis of the thermohydraulic data permitted characterization of the leakage through typical cracks that can occur in the pressurized tubes of the SG. Analysis of the data acquired by microphones and accelerometers highlighted that it is possible to correlate the signals to the leakage and the rate of release.

中文翻译:

使用 LIFUS5/Mod3 设施对 HLM 池中的泄漏检测系统进行实验表征

摘要 在欧盟 MAXSIMA 项目的框架内,研究了重液态金属快堆主回路中采用的蒸汽发生器 (SG) 的安全性,研究了 SG 管破裂事件的后果和损坏传播以及表征泄漏。典型裂缝的比率。可以使用能够迅速检测到 SG 管中裂纹存在的仪器来防止其进一步扩展,这将导致管完全破裂。先泄漏概念的应用与提高反应堆系统的安全性和降低管道破裂事件的可能性有关。在此框架中,已在安装在 ENEA Centro Ricerche Brasimone 的 LIFUS5/Mod3 设施中进行了一项新的实验活动(测试系列 C),为了表征和关联通过加压管中发生的典型裂缝的泄漏率与适当的传感器检测到的信号。测试 C1.3_60 是在大约 20 巴和 200°C 下将水注入铅铋共晶合金中进行的。通过直径为 60 μm 的激光微孔板进行注射。对热工水力数据的分析允许表征通过 SG 加压管中可能发生的典型裂缝的泄漏。对麦克风和加速度计获取的数据的分析表明,可以将信号与泄漏和释放速率相关联。执行 3_60 将约 20 巴和 200°C 的水注入铅铋共晶合金中。通过直径为 60 μm 的激光微孔板进行注射。对热工水力数据的分析允许表征通过 SG 加压管中可能发生的典型裂缝的泄漏。对麦克风和加速度计获取的数据的分析表明,可以将信号与泄漏和释放速率相关联。执行 3_60 将约 20 巴和 200°C 的水注入铅铋共晶合金中。通过直径为 60 μm 的激光微孔板进行注射。对热工水力数据的分析允许表征通过 SG 加压管中可能发生的典型裂缝的泄漏。对麦克风和加速度计获取的数据的分析表明,可以将信号与泄漏和释放速率相关联。
更新日期:2020-06-30
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