Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Prismatic-core advanced high temperature reactor and thermal energy storage coupled system - A preliminary design

  • Alameri, Saeed A. (Department of Nuclear Engineering, Khalifa University of Science and Technology) ;
  • King, Jeffrey C. (Nuclear Science and Engineering Program, Department of Metallurgical and Materials Engineering, Colorado School of Mines) ;
  • Alkaabi, Ahmed K. (Department of Nuclear Engineering, Khalifa University of Science and Technology) ;
  • Addad, Yacine (Department of Nuclear Engineering, Khalifa University of Science and Technology)
  • Received : 2019.04.15
  • Accepted : 2019.07.27
  • Published : 2020.02.25
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Abstract

This study presents an initial design for a novel system consisting in a coupled nuclear reactor and a phase change material-based thermal energy storage (TES) component, which acts as a buffer and regulator of heat transfer between the primary and secondary loops. The goal of this concept is to enhance the capacity factor of nuclear power plants (NPPs) in the case of high integration of renewable energy sources into the electric grid. Hence, this system could support in elevating the economics of NPPs in current competitive markets, especially with subsidized solar and wind energy sources, and relatively low oil and gas prices. Furthermore, utilizing a prismatic-core advanced high temperature reactor (PAHTR) cooled by a molten salt with a high melting point, have the potential in increasing the system efficiency due to its high operating temperature, and providing the baseline requirements for coupling other process heat applications. The present research studies the neutronics and thermal hydraulics (TH) of the PAHTR as well as TH calculations for the TES which consists of 300 blocks with a total heat storage capacity of 150 MWd. SERPENT Monte Carlo and MCNP5 codes carried out the neutronics analysis of the PAHTR which is sized to have a 5-year refueling cycle and rated power of 300 MWth. The PAHTR has 10 metric tons of heavy metal with 19.75 wt% enriched UO2 TRISO fuel, a hot clean excess reactivity and shutdown margin of $33.70 and -$115.68; respectively, negative temperature feedback coefficients, and an axial flux peaking factor of 1.68. Star-CCM + code predicted the correct convective heat transfer coefficient variations for both the reactor and the storage. TH analysis results show that the flow in the primary loop (in the reactor and TES) remains in the developing mixed convection regime while it reaches a fully developed flow in the secondary loop.

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References

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