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- W4223897753 abstract "This paper focuses on the development and demonstration of a modern thermal–hydraulic engineering tool to design nuclear thermal propulsion reactors. Low enriched uranium nuclear thermal propulsion reactors are currently being invested to appease regulatory and proliferation concerns, and consequently rendering the previous highly enriched uranium designs inapplicable. Sparse experimental data from the previously designed highly enriched uranium designs may be non-ideal for benchmarking low-enriched uranium designs. Computational fluid dynamics codes provide an affordable and expeditious alternate route for the verification of thermal–hydraulic engineering tools. Verification of engineering tools is crucial as they will be implemented in coupled neutronic and thermal–hydraulic simulations to ascertain the thermal and safety margins of a given design. Extensive research was performed on the optimization and design of nuclear thermal propulsion reactors, but there is limited publicly available description of currently adopted thermal–hydraulic solution procedures used for the design of contemporary nuclear thermal propulsion reactors. More specifically, the modelling assumptions, geometric simplifications, correlations, and iterative procedures are not always well understood or documented. The purpose of this paper is to provide a clear explanation of our thermal hydraulic modelling approach, clarify the impacts of commonly used assumptions on engineering-based tools, and demonstrate the importance of thermal–hydraulic solutions on neutronics. These objectives are achieved through the newly developed ntpThermo computational tool. This tool is verified against the high-order computational fluid dynamics code OpenFoam, which serves as the reference solution following a successful validation against experimental data. The results indicate that the reduced order-modeling approach implemented in ntpThermo can provide valuable engineering design support and be used for coupled neutronic and thermal–hydraulic simulations." @default.
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- W4223897753 date "2022-08-01" @default.
- W4223897753 modified "2023-10-02" @default.
- W4223897753 title "Thermal hydraulic modeling of solid fueled nuclear thermal propulsion reactors Part I: Development and verification" @default.
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- W4223897753 doi "https://doi.org/10.1016/j.anucene.2022.109113" @default.
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