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Thermal study of the emergency draining tank of molten salt reactor

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초록

In the framework of the European project SAMOSAFER, this numerical study focuses on some thermal aspects of the Emergency Draining Tank (EDT) located underneath the core of a Molten Salt Reactor. In case of an emergency, this tank passively receives the liquid fuel salt and is designed to ensure a subcritical state. An important requirement is that the fuel does not overheat to maintain the EDT Hastelloy container integrity. The present EDT is based upon a group of hexagonal cooling assemblies arranged in a hexagonal grid and cooled down thanks to conduction through the inert salt layer up to an air flow in charge of removing the heat. This numerical thermal study relies on a conjugated heat transfer analysis coupling a Finite Element solid thermal code (SYRTHES) and two instances of a Finite Volume CFD codes (Code_Saturne). Calculations on an initial design suggest that a simple center airpipe flow is likely to not sufficiently cool the device. Alternative solutions have been evaluated. Introduction of fins to enhance the heat transfer do not bring a noticeable improvement regarding maximum temperature reached. However, a solution in which the central pipe air flow is replaced by several cooling channels located closer to the fuel is investigated and suggests a better cooling.

Abstract

In the framework of the European project SAMOSAFER, this numerical study focuses on some thermal aspects of the Emergency Draining Tank (EDT) located underneath the core of a Molten Salt Reactor. In case of an emergency, this tank passively receives the liquid fuel salt and is designed to ensure a subcritical state. An important requirement is that the fuel does not overheat to maintain the EDT Hastelloy container integrity. The present EDT is based upon a group of hexagonal cooling assemblies arranged in a hexagonal grid and cooled down thanks to conduction through the inert salt layer up to an air flow in charge of removing the heat. This numerical thermal study relies on a conjugated heat transfer analysis coupling a Finite Element solid thermal code (SYRTHES) and two instances of a Finite Volume CFD codes (Code_Saturne). Calculations on an initial design suggest that a simple center airpipe flow is likely to not sufficiently cool the device. Alternative solutions have been evaluated. Introduction of fins to enhance the heat transfer do not bring a noticeable improvement regarding maximum temperature reached. However, a solution in which the central pipe air flow is replaced by several cooling channels located closer to the fuel is investigated and suggests a better cooling.

참고문헌 (13)

  1. Nuttin, "Potential of thorium molten salt reactors : detailed calculations and concept evolution with a view to large scale energy production", Prog. Nucl. Energy, 46, pp.77~99 (2005)
  2. D1.1 Description of Initial Reference Design and Identification of Safety Aspects, A Paradigm Shift in Nuclear Reactor Safety with the Molten Salt, "M. Allibert", ~, pp.FAST REACTOR (GRANT AGREEMENT 661891)- SAMOFAR (2017)
  3. SAMOSAFER European project (Number, Severe Accident Modeling and Safety Assessment for Fluid-Fuel Energy Reactor, , 847527~, pp.NFRP-2018 (2018)
  4. M. Massone, "Dimensioning of the emergency draining tank for a molten salt reactor through analytical modeling", Ann. Nucl. Energy, 138, pp.107121~ (2020)
  5. D. Gerardin, "D´eveloppement de m´ethodes et d’outils num´eriques pour l’´etude de la sûret´e du r´eacteur `a sels fondus MSFR", PhD, pp.2018
  6. "SALOME open-source CAD and meshing platform"[URL]
  7. I. Rupp, "Coupling heat conduction radiation and convection in complex geometries", Int Journal of Numerical Methods in complex geometries, Methods for Heat and fluid Flow, 9, pp.240~256 (1999), University Press
  8. "SYRTHES : open-source thermal code"[URL]
  9. "CODE_SATURNE open-source CFD code"[URL]
  10. F. Archambeau, "Code_Saturne : a finite volume code for the computation of turbulent incompressible flow – international", Journal of finite volumes
  11. R. Siegel, "Thermal Radiation Heat Transfer" (1981), Publishing Corporation
  12. D. J. Rogers, "Fusion properties and heat capacities of the eutectic LiF-NaK-KF melt", J. Chem. Eng. Data, 27, pp.366~367 (1982)
  13. G. Vidalain, "An enhanced thermal conduction model for the prediction of convection dominated solid-liquid phase change", Int. J. Heat Mass Tran, 52(7-8), pp.1753~1760 (2009)

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