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Research Articles – Selected papers from the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project special issue

Development of a Benchmark for Thermal Striping in Gas-Cooled Fast Reactors

ORCID Icon, , , , &
Received 11 Apr 2023, Accepted 25 Mar 2024, Published online: 25 Apr 2024
 

Abstract

This paper presents the development of a benchmark for predicting thermal striping through simulation. This work utilized large eddy simulation and will be used to benchmark future models. The testing domain was created using both the STRUCT and the Reynolds-averaged Navier-Stokes turbulence models and is based on an earlier design of the General Atomics Fast Modular Reactor upper plenum. The plenum features two adjacent, identical hexagonal bundles each with a center-placed axial rod drive, with a hot left coolant stream and a cold right coolant stream. The simulation solves the nondimensional Navier-Stokes equations, with temperature accounted as a passive scalar. First- and second-order flow statistics were obtained after 600 convective time units of averaging. The first-order statistics reveal that the hot jet is damped by a recirculatory flow from the near wall. At the same location, the second-order statistics show strong oscillations both in velocity and temperature. The power spectral density was utilized to determine that a low-frequency oscillation occurs here that is within the range of interest for thermal striping. Furthermore, proper orthogonal decomposition was used to identify coherent structures that confirm the oscillatory behavior, indicative of thermal striping. Overall, this benchmark can aid in the development of future models for predicting thermal striping in nuclear reactors, potentially leading to improved reactor safety and performance.

Disclosure Statement

No potential conflict of interest was reported by the author(s).

Additional information

Funding

This work was supported by the DOE Office of Nuclear Energy NEAMS program through the Center of Excellence for Thermal-fluid Applications in Nuclear Energy [DEAC02-06CH11357].

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