TY - GEN
T1 - NEAMS IRP Challenge Problem 2
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
AU - Baglietto, Emilio
AU - Acierno, John
AU - Manera, Annalisa
AU - Nguyen, Quynh M.
AU - Petrov, Victor
AU - Pham, Monica
AU - Wang, Yu Jou
AU - Jin, Yue
AU - Feng, Jinyong
AU - Strasser, Wayne
AU - Shaver, Dillon
AU - Merzari, Elia
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - Coolant flow in advanced reactors can be characterized by oscillatory mixing of non-isothermal liquid coolant streams, and is a potential cause of thermal fatigue damage in fuel and reactor components. The NEAMS IRP Challenge Problem 2 (CP2) seeks to develop an accurate, yet computationally affordable, turbulence modeling option for thermal-striping predictions. The designs of upper internal structures, as well as lower plena and heat exchanger configurations, are strongly affected by the ability to efficiently mix the coolant streams and further affects the material selection as well as operation and maintenance of the systems. This challenge problem generalizes specific needs related to the TerraPower and General Atomics designs by developing a set of benchmarks in order to advance, demonstrate and quantify the accuracy of the thermal striping modeling approach. The focus of the activities is to advance and demonstrate a modeling practice capable of accurately representing the performance of the structural reactor components under the influence of thermal striping. Assessment against adiabatic quasi-2D jets striping has demonstrated great promise for the proposed turbulence approaches, with 2 orders of magnitude acceleration from the reference Large Eddy Simulation (LES) solution. More recent efforts have extended the quasi-2D validation to diabatic conditions, leveraging the demonstrated accuracy of the highly resolved LES methods, and with a new set of experimental data for heated parallel round jets. Further upscaling through the use of reduced order models is being evaluated, and a two-step machine learning approach has been demonstrated on thermal striping for 3 parallel jets.
AB - Coolant flow in advanced reactors can be characterized by oscillatory mixing of non-isothermal liquid coolant streams, and is a potential cause of thermal fatigue damage in fuel and reactor components. The NEAMS IRP Challenge Problem 2 (CP2) seeks to develop an accurate, yet computationally affordable, turbulence modeling option for thermal-striping predictions. The designs of upper internal structures, as well as lower plena and heat exchanger configurations, are strongly affected by the ability to efficiently mix the coolant streams and further affects the material selection as well as operation and maintenance of the systems. This challenge problem generalizes specific needs related to the TerraPower and General Atomics designs by developing a set of benchmarks in order to advance, demonstrate and quantify the accuracy of the thermal striping modeling approach. The focus of the activities is to advance and demonstrate a modeling practice capable of accurately representing the performance of the structural reactor components under the influence of thermal striping. Assessment against adiabatic quasi-2D jets striping has demonstrated great promise for the proposed turbulence approaches, with 2 orders of magnitude acceleration from the reference Large Eddy Simulation (LES) solution. More recent efforts have extended the quasi-2D validation to diabatic conditions, leveraging the demonstrated accuracy of the highly resolved LES methods, and with a new set of experimental data for heated parallel round jets. Further upscaling through the use of reduced order models is being evaluated, and a two-step machine learning approach has been demonstrated on thermal striping for 3 parallel jets.
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U2 - 10.13182/NURETH20-40694
DO - 10.13182/NURETH20-40694
M3 - Conference contribution
AN - SCOPUS:85202911916
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 4464
EP - 4475
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
Y2 - 20 August 2023 through 25 August 2023
ER -