TY - GEN
T1 - CHF Prediction During an RIA With a BISON and THM Coupled Model
AU - Aldeia Machado, L. C.
AU - Merzari, E.
AU - Walters, W.
AU - Charlot, L.
N1 - Publisher Copyright:
© 2023 Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023. All rights reserved.
PY - 2023
Y1 - 2023
N2 - A Reactivity-Initiated Accident (RIA) are design-basis accident that occurs when the reactor loses one of its control rods. A reactivity insertion will follow such events, drastically increasing the fuel pellet's temperature and volume due to thermal expansion. The fuel pellet and the cladding will interact mechanically, which could lead to cladding failure. The current limits for low-temperature clad failure during RIAs are outdated, obtained for fuels with a considerably lower burnup than the current fuels can reach. This work will focus on the thermal hydraulics behavior during the first stages of the RIA transient, when the clad temperature is still low, for high burnup fuels. We will show the results for a coupled BISON and MOOSE thermal hydraulics module (THM) model created to predict if we reach critical heat flux (CHF) during the power transient, which will characterize the end of the low-temperature phase during an RIA.
AB - A Reactivity-Initiated Accident (RIA) are design-basis accident that occurs when the reactor loses one of its control rods. A reactivity insertion will follow such events, drastically increasing the fuel pellet's temperature and volume due to thermal expansion. The fuel pellet and the cladding will interact mechanically, which could lead to cladding failure. The current limits for low-temperature clad failure during RIAs are outdated, obtained for fuels with a considerably lower burnup than the current fuels can reach. This work will focus on the thermal hydraulics behavior during the first stages of the RIA transient, when the clad temperature is still low, for high burnup fuels. We will show the results for a coupled BISON and MOOSE thermal hydraulics module (THM) model created to predict if we reach critical heat flux (CHF) during the power transient, which will characterize the end of the low-temperature phase during an RIA.
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U2 - 10.13182/NURETH20-40894
DO - 10.13182/NURETH20-40894
M3 - Conference contribution
AN - SCOPUS:85202948908
T3 - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
SP - 1121
EP - 1134
BT - Proceedings of the 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
PB - American Nuclear Society
T2 - 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2023
Y2 - 20 August 2023 through 25 August 2023
ER -