Hypothetical Core Disruptive Accidents (HCDA) are dominantly concerned during safety assessment and evaluation in Sodium-cooled Fast Reactor (SFR). With molten core materials discharged into liquid sodium, positive reactivity is potentially introduced due to sodium boiling and molten core compaction, which can cause terrible recriticality. The possibility of recriticality and efficient cooling on the relocated debris bed are significantly affected by the fragmentation behavior of molten core in liquid sodium. With few available mechanism models and benchmarks, many investigations have been conducted on the fragmentation characteristics during molten fuel-coolant interaction (MFCI). In the present study, molten copper is used for molten simulant to be discharged into the liquid sodium pool through guiding tube based on a multifunctional experimental facility (COSA). The simulants are heated by electromagnetic induction system in customized ceramic crucible and the molten materials are controlled by magnetic lifting system to be drained through the guiding tube into the bottom liquid sodium pool. Temperature variation and pressure change in the liquid sodium pool are acquired against the energy release during MFCI. Furthermore, the fragments cleaned by water medium are measured and recorded for distribution and morphology analysis. Significant pressure pulses and temperature gradient almost not occur during MFCI and the molten copper is finely fragmented possibly due to hydrodynamic and thermodynamic effects. And the experimental results are helpful to confirm the prediction of fragmentation mechanism and to validate physical model, which can be applied to the development and validation of analysis code.
Skip Nav Destination
2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5153-1
PROCEEDINGS PAPER
Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium Available to Purchase
Liang Hu,
Liang Hu
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
Kui Ge,
Kui Ge
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
Yapei Zhang,
Yapei Zhang
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
G. H. Su,
G. H. Su
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
Wenxi Tian,
Wenxi Tian
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
Suizheng Qiu
Suizheng Qiu
Xi'an Jiaotong University, Xi'an City, China
Search for other works by this author on:
Liang Hu
Xi'an Jiaotong University, Xi'an City, China
Kui Ge
Xi'an Jiaotong University, Xi'an City, China
Yapei Zhang
Xi'an Jiaotong University, Xi'an City, China
G. H. Su
Xi'an Jiaotong University, Xi'an City, China
Wenxi Tian
Xi'an Jiaotong University, Xi'an City, China
Suizheng Qiu
Xi'an Jiaotong University, Xi'an City, China
Paper No:
ICONE26-81400, V009T16A024; 5 pages
Published Online:
October 24, 2018
Citation
Hu, L, Ge, K, Zhang, Y, Su, GH, Tian, W, & Qiu, S. "Experimental Research on Energy Release and Fragments Characteristics Under Molten Materials Discharged Into Liquid Sodium." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 9: Student Paper Competition. London, England. July 22–26, 2018. V009T16A024. ASME. https://doi.org/10.1115/ICONE26-81400
Download citation file:
22
Views
Related Proceedings Papers
Related Articles
Surfactant-Based Cu–Water Nanofluid Spray for Heat Transfer Enhancement of High Temperature Steel Surface
J. Heat Transfer (May,2015)
Determination of Boiling Film Coefficient for a Heated Horizontal Tube in Water-Saturated Wick Material
J. Heat Transfer (February,1961)
LMFBR Loss of Flow Simulations in the Sodium Loop Safety Facility
J. Eng. Power (October,1981)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Comparison of the Availability of Trip Systems for Reactors with Exothermal Reactions (PSAM-0361)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies