{"title":"Spent fuel pool boil-off experiments with high power and high time resolution","authors":"Christoph Schuster , Oleg E. Stepanov","doi":"10.1016/j.nucengdes.2025.113958","DOIUrl":null,"url":null,"abstract":"<div><div>The occurrence of spent fuel pool (SFP) accidents, in which the water level decreases below the top of the fuel assemblies (FA), may arise due to the loss of active pool cooling or pool leakage. In such scenarios, the ALADIN test facility of the TUD Dresden University of Technology is utilized to simulate a comprehensive boiling water reactor (BWR) FA in a 1:1 scale. This report supplements the existing data base with rod powers between 100 W and 350 W. Boil-off experiments will be analyzed in detail in relation to axial and radial temperature profiles as a function of time and heater power up to a maximum temperature of approximately 800 °C. Additionally, temperature excursion mitigating measures such as spray-cooling and flooding will be discussed.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"435 ","pages":"Article 113958"},"PeriodicalIF":1.9000,"publicationDate":"2025-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325001359","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
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Abstract
The occurrence of spent fuel pool (SFP) accidents, in which the water level decreases below the top of the fuel assemblies (FA), may arise due to the loss of active pool cooling or pool leakage. In such scenarios, the ALADIN test facility of the TUD Dresden University of Technology is utilized to simulate a comprehensive boiling water reactor (BWR) FA in a 1:1 scale. This report supplements the existing data base with rod powers between 100 W and 350 W. Boil-off experiments will be analyzed in detail in relation to axial and radial temperature profiles as a function of time and heater power up to a maximum temperature of approximately 800 °C. Additionally, temperature excursion mitigating measures such as spray-cooling and flooding will be discussed.
期刊介绍：
Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.
Fundamentals of Reactor Design include:
• Thermal-Hydraulics and Core Physics
• Safety Analysis, Risk Assessment (PSA)
• Structural and Mechanical Engineering
• Materials Science
• Fuel Behavior and Design
• Structural Plant Design
• Engineering of Reactor Components
• Experiments
Aspects beyond fundamentals of Reactor Design covered:
• Accident Mitigation Measures
• Reactor Control Systems
• Licensing Issues
• Safeguard Engineering
• Economy of Plants
• Reprocessing / Waste Disposal
• Applications of Nuclear Energy
• Maintenance
• Decommissioning
Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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