TY - GEN
T1 - Multi-physics Modeling of Radiative Heat Transfer and Fluid Flow for the Reactor Cavity Cooling System
AU - Okyay, Sinan
AU - Leite, Victor Coppo
AU - Merzari, Elia
AU - Balestra, Paolo
AU - Strydom, Gerhard
N1 - Publisher Copyright:
© Proceedings of Advances in Thermal Hydraulics, ATH 2024.
PY - 2024
Y1 - 2024
N2 - High-temperature gas-cooled reactors (HTGRs) are notable for their high thermal efficiency and potential for combined heat and power applications. These reactors are particularly appealing due to their advanced passive safety features. HTGRs utilize passive safety systems that function without requiring active components like pumps or compressors during emergencies. These reactor designs depend on a Reactor Cavity Cooling System (RCCS) to manage decay heat removal from the reactor pressure vessel (RPV) during accident conditions. The RCCS consists of vertical rectangular channels known as”risers” or riser ducts positioned around the RPV. These risers receive heat from the RPV through both convective and radiative heat transfer mechanisms. Understanding the of multiple physical phenomena, such as fluid dynamics, heat transfer, and neutron interactions, is essential for the interplay effective design and operation of nuclear reactors, particularly for systems like the RCCS. Multi-physics simulations provide a comprehensive approach to studying these interactions, offering detailed insights and enhancing accuracy. They are especially important in RCCS where the interaction between radiative and convective heat transfer can significantly impact system performance. designs, By leveraging multi-physics simulations, complex reactor behaviors can be modeled without compromising the fidelity of the underlying physical processes. This work aims to establish a robust methodology for coupling multiple physical processes in an air-cooled RCCS. By focusing on validating this multi-physics approach, the study involves designing test cases that simulate various conditions to verify the numerical models employed. The outcomes of this research will provide critical insights for accurately modeling and optimizing complex nuclear systems like the RCCS.
AB - High-temperature gas-cooled reactors (HTGRs) are notable for their high thermal efficiency and potential for combined heat and power applications. These reactors are particularly appealing due to their advanced passive safety features. HTGRs utilize passive safety systems that function without requiring active components like pumps or compressors during emergencies. These reactor designs depend on a Reactor Cavity Cooling System (RCCS) to manage decay heat removal from the reactor pressure vessel (RPV) during accident conditions. The RCCS consists of vertical rectangular channels known as”risers” or riser ducts positioned around the RPV. These risers receive heat from the RPV through both convective and radiative heat transfer mechanisms. Understanding the of multiple physical phenomena, such as fluid dynamics, heat transfer, and neutron interactions, is essential for the interplay effective design and operation of nuclear reactors, particularly for systems like the RCCS. Multi-physics simulations provide a comprehensive approach to studying these interactions, offering detailed insights and enhancing accuracy. They are especially important in RCCS where the interaction between radiative and convective heat transfer can significantly impact system performance. designs, By leveraging multi-physics simulations, complex reactor behaviors can be modeled without compromising the fidelity of the underlying physical processes. This work aims to establish a robust methodology for coupling multiple physical processes in an air-cooled RCCS. By focusing on validating this multi-physics approach, the study involves designing test cases that simulate various conditions to verify the numerical models employed. The outcomes of this research will provide critical insights for accurately modeling and optimizing complex nuclear systems like the RCCS.
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U2 - 10.13182/T131-45630
DO - 10.13182/T131-45630
M3 - Conference contribution
AN - SCOPUS:85216025213
T3 - Proceedings of Advances in Thermal Hydraulics, ATH 2024
SP - 376
EP - 389
BT - Proceedings of Advances in Thermal Hydraulics, ATH 2024
PB - American Nuclear Society
T2 - 2024 Advances in Thermal Hydraulics, ATH 2024
Y2 - 17 November 2024 through 21 November 2024
ER -