Thermal and hydraulic performance of volumetrically heated triply periodic minimal surface heaters

被引:1
作者
Prussack, Brett [1 ]
Jentz, Ian [1 ]
Moreira, Tiago A. [1 ]
Woolstenhulme, Nicolas [2 ]
Jesse, Casey [2 ]
Nellis, Greg [1 ]
Anderson, Mark [1 ]
机构
[1] Univ Wisconsin Madison, Dept Mech Engn, Thermal Hydraul Lab, 1500 Engn Dr, Madison, WI 53706 USA
[2] Idaho Natl Lab, Nucl Fuels & Mat Div, Idaho Falls, ID 83415 USA
关键词
Thermal -hydraulic characterization; Triply periodic minimal surface; Heat exchanger; Forced convection; Nuclear fuel lattice; Additive manufacturing;
D O I
10.1016/j.applthermaleng.2024.123291
中图分类号
O414.1 [热力学];
学科分类号
摘要
Advanced heat transfer surfaces, mainly Triply Periodic Minimal Surfaces (TPMSs) have great potential to increase heat transfer performance over traditional heat transfer surfaces due to their tortuous flow path and higher surface area-volume ratio. The emergence of additive manufacturing of nuclear fuel motivates experimental investigation of such advanced geometries in the context of a nuclear reactor core. This study employed a novel method to explore the performance of gyroid and diamond TPMS geometries. Volumetrically heated heaters were additively manufactured from conductive polymer filament, and airflow was used to simulate the convective heat transfer from the core within a nuclear reactor. The mass flow and volumetric generation rates were varied, local Nusselt number correlations were obtained using embedded thermocouples to measure the solid and fluid temperature, and friction factor correlations were developed using differential pressure measurements. The gyroid TPMS presented a friction factor 1.5 times higher than the diamond TPMS and 90 times that of the rod bundle. TPMS geometries showed Nusselt numbers 8-10 times higher than that of the rod bundle, also maintaining colder internal temperatures, which suggested that they could sustain 250-275 % higher power density than the rod bundle for a given centerline temperature. Hence, having the potential to greatly increase the safety margins and power output of a nuclear reactor core with similar volume.
引用
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页数:14
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