EXPERIMENTAL INVESTIGATION ON STEAM GENERATOR TUBE RUPTURE (SGTR) ACCIDENT OF LEAD-COOLED FAST REACTORS BASED ON LEST FACILITY
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- Yu Qifan
- Department of Nuclear Science and Technology Jiaotong University
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- Zhao Yafeng
- Department of Nuclear Science and Technology
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- Qiu Suizheng
- Department of Nuclear Science and Technology
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- Wang Chenglong
- Department of Nuclear Science and Technology
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- Zhang Dalin
- Department of Nuclear Science and Technology
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- Tian Wenxi
- Department of Nuclear Science and Technology
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- SU G. H.
- Department of Nuclear Science and Technology
Abstract
<p>Whole process exploration and transient thermal-hydraulic parameters acquisition of Steam Generator Tube Rupture (SGTR) Accident are of significant importance for safety analysis of Lead-cooled Fast Reactors (LFRs). The Lead-bismuth Eutectic Steam generator tube rupture Test facility (LEST) for transient experiments of lead-based eutectic (LBE)-water-steam three-phase was built. Three thermal-hydraulic phenomena were analyzed. These include 1) initial pressure peak measured and pressure attenuation equations fitted, 2) LBE pressure rising curves and its equilibrium with water side, 3) steam cavity migration monitored by thermocouples. The latest results showed that the accident pressure in LBE side rose with a higher water initial pressure 7.5MPa. The attenuation curve of pressure peak was represented by simple harmonic vibration. Besides, the injection of supercooled water incurred temperature fluctuations in LBE pool, with an instantaneous 81.6 ℃ temperature drop near the injection nozzle, and then LBE temperature re-entered a new dynamic equilibrium.</p>
Journal
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- The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2023.30 (0), 1095-, 2023
The Japan Society of Mechanical Engineers
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Details 詳細情報について
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- CRID
- 1390016803389553408
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- ISSN
- 24242934
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- Text Lang
- en
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- Data Source
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- JaLC
- Crossref
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- Abstract License Flag
- Disallowed