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Advanced Multiphysics Code Coupling for Cladding Surface Thermocouples During Two-Phase Heat Transfer from Nuclear Fuel

Armstrong, Robert [Idaho National Laboratory (INL), Idaho Falls, ID (United States); Univ. of Wisconsin, Madison, WI (United States)] (ORCID:0000000178753828)·Vermaak, Jan [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]·Folsom, Charles [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000282428777)·Seo, Seokbin [Idaho National Laboratory (INL), Idaho Falls, ID (United States)]·Pacheco Duarte, Juliana [Univ. of Wisconsin, Madison, WI (United States)] (ORCID:0000000307261564)·Jensen, Colby [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000189257758)
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Abstract

Transient testing of nuclear fuel involves the evaluation of fuel performance under off-normal and accident conditions and is essential for proving design performance. Instrumentation included in such experiments commonly includes thermocouples attached to the outer surface of the cladding to provide temperature measurements throughout the transient. However, the presence of thermocouples on the cladding surface can alter the local heat transfer characteristics with the surrounding coolant. These localized effects can influence the temperature of the nearby cladding surface and introduce uncertainties in interpreting the thermocouple data. Understanding the impact of thermocouples attached to the outer surface of the cladding is crucial for accurate data interpretation as well as its effect on the thermomechanical behavior of the cladding. This paper presents a novel methodology for simulating the impact of outer cladding thermocouples during transient testing of nuclear fuels. The simulation framework leverages the thermal-hydraulic capabilities of RELAP5-3D coupled to the BISON fuel performance code through the RELAPCouplingApp interface. The methodology is compared against Accident Tolerant Fuel Reactivity Initiated Accident-1-E experiment performed at Idaho National Laboratory. The results reveal approximately 100°C difference between thermocouple-altered temperature and virgin cladding surface. The model overpredicts surface rewet time due to conservative correlations.

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11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS11 NUCLEAR FUEL CYCLE AND FUEL MATERIALSBISONRELAP5-3DTransient Reactor Test Facilityreactivity-initiated accident

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Armstrong, Robert [Idaho National Laboratory (INL), Idaho Falls, ID (United States); Univ. of Wisconsin, Madison, WI (United States)] (ORCID:0000000178753828), Vermaak, Jan [Idaho National Laboratory (INL), Idaho Falls, ID (United States)], Folsom, Charles [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000282428777), Seo, Seokbin [Idaho National Laboratory (INL), Idaho Falls, ID (United States)], Pacheco Duarte, Juliana [Univ. of Wisconsin, Madison, WI (United States)] (ORCID:0000000307261564), Jensen, Colby [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000189257758). 2026-02-17. Advanced Multiphysics Code Coupling for Cladding Surface Thermocouples During Two-Phase Heat Transfer from Nuclear Fuel. https://doi.org/10.1080/00295450.2025.2593797

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