Effect of metal layer height on heat transfer inside molten pool
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Chang Liu
,
Pengfei Ma
and
Liuxuan Cao
Abstract
In a serious accident, after the core of a nuclear reactor melts and collapses, In-Vessel Retention in the External Reactor Vessel Cooling (IVR-ERVC) is an effective technology to maintain the integrity of lower head by reducing heat load on it. The various factors affecting the melting of the lower head have been widely studied. The mass of the molten metal layer may affect the consequences of the accident, since it is where the focusing effect occurs. However, the related research is still absent. In this paper, we systematically calculated the heat transfer behavior and melting process under different metal layer heights conditions. The temperature distribution, the velocity distribution, the heat flux of the outer wall of the Reactor Pressure Vessel (RPV), and the change of the thickness of the RPV were obtained through Large Eddy Simulation (LES). Interestingly, the heat flux increases with the metal layer height at first and achieve the maximum in the middle height. These results increase the understanding towards the serious accidents.
Funding source: XMU Training Program of Innovation and Entrepreneurship for Undergraduates
Award Identifier / Grant number: NO. 2021X1173, NO. 2021Y1337
Funding source: National Natural Science Foundation of China
Award Identifier / Grant number: NO. 12175188
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This research was supported by the National Natural Science Foundation of China (NO. 12175188), and XMU Training Program of Innovation and Entrepreneurship for Undergraduates (NO. 2021X1173 and NO. 2021Y1337).
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events
Articles in the same Issue
- Frontmatter
- Effect of engraved concentric circles on pool boiling of water
- Numerical determination of condensation pressure drop of various refrigerants in smooth and micro-fin tubes via ANN method
- Effect of metal layer height on heat transfer inside molten pool
- Transient analysis of MTR research reactor during fast and slow loss of flow accident
- Determination of heat flux leading to the onset of flow instability in MTR reactors
- Experimental study on direct contact condensation of saturated steam at low mass flux in subcooled quiescent water
- Evaluation and integral analysis of ADS and CMT failures during AP1000 SBLOCA with ASYST VER 3 simulation code
- Computational fluid dynamics simulation of material testing reactor spent fuel cooling in wet storage
- The role of advanced nuclear reactors in non-electrical and strategic applications, producing sustainable energy supplies and reducing the greenhouse gasses
- Optimization of PID controller for water level control of the nuclear steam generator using PSO and GA
- Assessment for nuclear security using Analytic Hierarchy Process (AHP) incorporated with Neural Networking Method in nuclear power plants (NPPs)
- Safety assessment and management of spent nuclear fuel for TRIGA mark II research reactor
- Calendar of events
