{"title":"不同熔融金属与硅铁混凝土相互作用过程中温度分布的测量和界面热流密度分布的估计","authors":"Pedduri Jayakrishna , Akshay U. Shirsat , Prakash Nanthagopalan , Arunkumar Sridharan , Shyamprasad Karagadde , Anuj Kumar Deo , Srinivasa Rao , P.K. Baburajan , S.V. Prabhu","doi":"10.1016/j.nucengdes.2025.114099","DOIUrl":null,"url":null,"abstract":"<div><div>The necessity of understanding the interaction of molten corium with the sacrificial concrete layer surrounding the nuclear reactors has been the motivation to perform MCCI experiments. Materials (zinc, aluminium and stainless steel) which have different melting temperatures and thermal properties are chosen and the experimental investigations are carried out by pouring molten metals in well-defined cavities of concrete test sections to study the ablation and thermal behaviour of the concrete. Coarse and fine aggregates of hematite are added to the cement to attain the required mechanical and thermal properties and provide better radiation shielding. The transient interaction of the molten metal with the concrete is measured using thermocouples. The measured subsurface temperatures are subsequently used to estimate the interfacial heat flux profiles by solving an inverse heat conduction problem using the sequential function specification method. The peak temperatures measured and peak heat flux values estimated in concrete samples interacted with zinc, aluminium and stainless steel are around 85 °C and 35 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, 105 °C and 58 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, and 468 °C and 65 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, respectively. There is no ablation during the interaction of zinc and aluminium with the concrete test sections. Though the melting temperature of stainless steel (1450 °C) is higher than the ablation temperature of the concrete (around 1200 °C), concrete did not undergo significant ablation due to the higher density and the strength offered by the addition of hematite aggregates. The results presented in the current study are accurate within the time period where the semi-infinite model is valid.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"439 ","pages":"Article 114099"},"PeriodicalIF":1.9000,"publicationDate":"2025-05-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Measurement of temperature distribution and estimation of interfacial heat flux profiles during the interaction of different molten metals with ferrosiliceous concrete\",\"authors\":\"Pedduri Jayakrishna , Akshay U. Shirsat , Prakash Nanthagopalan , Arunkumar Sridharan , Shyamprasad Karagadde , Anuj Kumar Deo , Srinivasa Rao , P.K. Baburajan , S.V. Prabhu\",\"doi\":\"10.1016/j.nucengdes.2025.114099\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The necessity of understanding the interaction of molten corium with the sacrificial concrete layer surrounding the nuclear reactors has been the motivation to perform MCCI experiments. Materials (zinc, aluminium and stainless steel) which have different melting temperatures and thermal properties are chosen and the experimental investigations are carried out by pouring molten metals in well-defined cavities of concrete test sections to study the ablation and thermal behaviour of the concrete. Coarse and fine aggregates of hematite are added to the cement to attain the required mechanical and thermal properties and provide better radiation shielding. The transient interaction of the molten metal with the concrete is measured using thermocouples. The measured subsurface temperatures are subsequently used to estimate the interfacial heat flux profiles by solving an inverse heat conduction problem using the sequential function specification method. The peak temperatures measured and peak heat flux values estimated in concrete samples interacted with zinc, aluminium and stainless steel are around 85 °C and 35 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, 105 °C and 58 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, and 468 °C and 65 <span><math><mrow><mi>k</mi><mi>W</mi><mo>/</mo><msup><mrow><mi>m</mi></mrow><mn>2</mn></msup></mrow></math></span>, respectively. There is no ablation during the interaction of zinc and aluminium with the concrete test sections. Though the melting temperature of stainless steel (1450 °C) is higher than the ablation temperature of the concrete (around 1200 °C), concrete did not undergo significant ablation due to the higher density and the strength offered by the addition of hematite aggregates. The results presented in the current study are accurate within the time period where the semi-infinite model is valid.</div></div>\",\"PeriodicalId\":19170,\"journal\":{\"name\":\"Nuclear Engineering and Design\",\"volume\":\"439 \",\"pages\":\"Article 114099\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-05-02\",\"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/S0029549325002766\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325002766","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}
Measurement of temperature distribution and estimation of interfacial heat flux profiles during the interaction of different molten metals with ferrosiliceous concrete
The necessity of understanding the interaction of molten corium with the sacrificial concrete layer surrounding the nuclear reactors has been the motivation to perform MCCI experiments. Materials (zinc, aluminium and stainless steel) which have different melting temperatures and thermal properties are chosen and the experimental investigations are carried out by pouring molten metals in well-defined cavities of concrete test sections to study the ablation and thermal behaviour of the concrete. Coarse and fine aggregates of hematite are added to the cement to attain the required mechanical and thermal properties and provide better radiation shielding. The transient interaction of the molten metal with the concrete is measured using thermocouples. The measured subsurface temperatures are subsequently used to estimate the interfacial heat flux profiles by solving an inverse heat conduction problem using the sequential function specification method. The peak temperatures measured and peak heat flux values estimated in concrete samples interacted with zinc, aluminium and stainless steel are around 85 °C and 35 , 105 °C and 58 , and 468 °C and 65 , respectively. There is no ablation during the interaction of zinc and aluminium with the concrete test sections. Though the melting temperature of stainless steel (1450 °C) is higher than the ablation temperature of the concrete (around 1200 °C), concrete did not undergo significant ablation due to the higher density and the strength offered by the addition of hematite aggregates. The results presented in the current study are accurate within the time period where the semi-infinite model is valid.
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.