Improved natural convection heat transfer correlations for reactor cavity cooling systems of high-temperature gas-cooled reactors: From computational fluid dynamics to Pronghorn
被引:5
作者:
Freile, Ramiro
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Texas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USATexas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Freile, Ramiro
[1
]
Tano, Mauricio
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Texas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USATexas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Tano, Mauricio
[1
]
Balestra, Paolo
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Idaho Natl Lab, 775 MK Simpson Blvd, Idaho Falls, ID 83401 USATexas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Balestra, Paolo
[2
]
Schunert, Sebastian
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Idaho Natl Lab, 775 MK Simpson Blvd, Idaho Falls, ID 83401 USATexas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Schunert, Sebastian
[2
]
Kimber, Mark
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Texas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Texas A&M Univ, Dept Mech Engn, 3127 TAMU, College Stn, TX 77843 USATexas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
Kimber, Mark
[1
,3
]
机构:
[1] Texas A&M Univ, Dept Nucl Engn, 423 Spence St, College Stn, TX 77843 USA
[2] Idaho Natl Lab, 775 MK Simpson Blvd, Idaho Falls, ID 83401 USA
[3] Texas A&M Univ, Dept Mech Engn, 3127 TAMU, College Stn, TX 77843 USA
Natural convection;
Heat transfer correlations;
High Rayleigh numbers;
Reactor cavity cooling system;
Pronghorn;
ENCLOSURES;
D O I:
10.1016/j.anucene.2021.108547
中图分类号:
TL [原子能技术];
O571 [原子核物理学];
学科分类号:
0827 ;
082701 ;
摘要:
The reactor cavity cooling system (RCCS) is a common reactor safety system in high-temperature gas-cooled Reactors (HTGR) that removes heat from the reactor pressure vessel (RPV) by radiation (similar to 80%) and natural convection (similar to 20%). For the simulation of accident scenarios of HTGRs, intermediate fidelity and system codes models must be employed to limit the models' execution time. While an accurate quantification of the radiative heat transfer is available in these models, the quantification of natural convection must rely on correlations of questionable accuracy for the Nusselt number. Commonly used correlations are based in experiments performed at low Rayleigh numbers and/or using isothermal walls in simplified geometries. This work improves on the accuracy of natural convection heat transfer correlations to support HTGR designs.These correlations include both local and average Nusselt numbers as a function of the global Rayleigh number, the local Rayleigh number, and the temperature profile at the hot wall of the RCCS. In the absence of dedicated experiments and the difficulty of performing high-fidelity simulations at realistic Rayleigh numbers, the data to fit the correlations are generated with computational fluid dynamics (CFD) using Reynolds Averaged Navier-Stokes (RANS) models. First, a careful selection of the RANS turbulence model is performed by comparing the results obtained with different RANS turbulence models against high-fidelity simulations of natural convection at Ra 1 x 10(11) in a rectangular cavity. Next, the selected model is used to perform simulations of an HTGR cavity at different high Rayleigh numbers is an element of [6.1 x 10(11) ,2.9 x 10(13)] to encompass several HTGR designs, assuming an isothermal RPV wall. The results obtained are used to fit a correlation for the average and space-varying Nusselt number as a function of the global and local Rayleigh numbers via a sparsity-promoting, least-squares method. The selected RANS model is then used to perform simulations of a PBMR-400 (Pebble Bed Modular Reactor) HTGR cavity with the temperature profiles at the RPV wall obtained during a PLOFC (Pressurized loss of forced cooling) transient. We use the results obtained to fit a temperature-dependent correction to the space-varying Nusselt number with the sparsity-promoting, least-squares method. The results obtained in this work enable system-level codes, such as Pronghorn, to perform higher-fidelity simulations of the heat exchange process in the RCCS while still maintaining a low computational cost. Published by Elsevier Ltd.
机构:
INDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIAINDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIA
BALAJI, C
VENKATESHAN, SP
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INDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIAINDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIA
机构:
Korea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South Korea
Choi, Seok-Ki
Kim, Seong-O
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机构:
Korea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South Korea
机构:
INDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIAINDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIA
BALAJI, C
VENKATESHAN, SP
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机构:
INDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIAINDIAN INST TECHNOL,DEPT MECH ENGN,HEAT TRANSFER & THERMAL POWER LAB,MADRAS 600036,TAMIL NADU,INDIA
机构:
Korea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South Korea
Choi, Seok-Ki
Kim, Seong-O
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机构:
Korea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South KoreaKorea Atom Energy Res Inst, Fast Reactor Dev Div, Taejon 305353, South Korea