A RELAP5-3D Model of the Lobo Lead Loop

Barthle, Jonathan L.; Meehan, Nicholas; Maldonado, G. Ivan; Brown, Nicholas R.

doi:10.1080/00295450.2024.2374661

A RELAP5-3D Model of the Lobo Lead Loop

Journal Article · Fri Jul 26 04:00:00 EDT 2024 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2024.2374661· OSTI ID:2437653

Barthle, Jonathan L. ^[1]; Meehan, Nicholas ^[2]; Maldonado, G. Ivan ^[2]; ^[2]

University of Tennessee, Knoxville, TN (United States); University of Tennessee
University of Tennessee, Knoxville, TN (United States)

The goal of our research is to build upon the capability of RELAP5-3D to model molten lead systems. Molten lead has several potential uses in future advanced reactors like the lead fast reactor or fusion reactors that utilize dual-coolant lead lithium blankets. This potential for use in future generations of reactors highlights the necessity to develop molten lead models to ensure that they can accurately predict the thermohydraulic behavior. We have developed a RELAP5-3D model of the Lobo Lead Loop facility, located at the University of New Mexico, to verify the accuracy of RELAP5-3D via comparison to existing computational fluid dynamics results and analytical calculations. It was found that RELAP5-3D accurately calculated radiative heat transfer (within < 1%) when compared to theoretical calculations. In addition, pressure drop calculations done in RELAP5-3D demonstrated reasonable agreement within 20 kPa, mostly within ~7-15%, when compared to the computational fluid dynamics model of the facility developed by the University of New Mexico, and captured the dependence of pressure drop on flow velocity accurately. Finally, a hypothetical loss of flow transient was imposed on the RELAP5-3D model to determine the feasibility of performing a similar experiment with the Lobo Lead Loop. It was found that such an experiment could be possible as the RELAP5-3D model indicated that the temperatures of the fluid would not exceed limiting temperatures of the structure (1658 K) nor the maximum temperature of the electromagnetic pump inlet (823 K). Although there is not experimental data to begin validation, the model will be readily available for future validation studies when the experimental data is generated, especially as the model continues to evolve over time. Furthermore, the results so far demonstrate a promising first step in the verification/validation of the RELAP5-3D model of the Lobo Lead Loop.

View Accepted Manuscript (DOE)

Research Organization:: University of Tennessee, Knoxville, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: SC0022308

OSTI ID:: 2437653

Journal Information:: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 5 Vol. 211; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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22 GENERAL STUDIES OF NUCLEAR REACTORS
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A RELAP5-3D Model of the Lobo Lead Loop

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