TY - JOUR
T1 - Thermal mixing and stratification in the liquid metal-cooled reactor pool experiment E-SCAPE
AU - Van Tichelen, Katrien
AU - Mirelli, Fabio
AU - Bartosiewicz, Yann
AU - D'haeseleer, William
N1 - Score=10
Publisher Copyright:
© 2024 Elsevier B.V.
PY - 2025/2
Y1 - 2025/2
N2 - Natural circulation in the primary system is the chosen option in terms of decay heat removal (DHR) for the liquid–metal cooled, pool-type research reactor MYRRHA, keeping temperatures in the core within the safety limits and maintaining structural integrity of the coolant boundaries. Experiments in E-SCAPE, the 1/6-scale 3-D model of the primary system of MYRRHA, demonstrate that in DHR conditions, a buoyancy-driven natural circulation flow establishes and is capable to remove the core power with temperatures that are within acceptable limits. The effects of the core power, the system pressure losses and the initial conditions on the flow and the temperatures are analyzed. The experiments show that, in natural circulation thermal stratification is present in the upper plenum. From forced circulation experiments in the same facility, one can conclude that good thermal mixing is obtained for forced flow rates above 40% of the nominal flow rate. Below this value, buoyancy becomes important and thermal stratification is observed in forced flow conditions as well. Results demonstrate that the Richardson number in the upper plenum RiUP can be used as an indicator for thermal stratification. For values below unity, good thermal mixing is observed. If RiUP is higher than 1, thermal stratification occurs.
AB - Natural circulation in the primary system is the chosen option in terms of decay heat removal (DHR) for the liquid–metal cooled, pool-type research reactor MYRRHA, keeping temperatures in the core within the safety limits and maintaining structural integrity of the coolant boundaries. Experiments in E-SCAPE, the 1/6-scale 3-D model of the primary system of MYRRHA, demonstrate that in DHR conditions, a buoyancy-driven natural circulation flow establishes and is capable to remove the core power with temperatures that are within acceptable limits. The effects of the core power, the system pressure losses and the initial conditions on the flow and the temperatures are analyzed. The experiments show that, in natural circulation thermal stratification is present in the upper plenum. From forced circulation experiments in the same facility, one can conclude that good thermal mixing is obtained for forced flow rates above 40% of the nominal flow rate. Below this value, buoyancy becomes important and thermal stratification is observed in forced flow conditions as well. Results demonstrate that the Richardson number in the upper plenum RiUP can be used as an indicator for thermal stratification. For values below unity, good thermal mixing is observed. If RiUP is higher than 1, thermal stratification occurs.
KW - Integral test facility
KW - Lead bismuth eutectic
KW - Liquid metal-cooled reactor
KW - Natural circulation
KW - Stratification
KW - Thermal hydraulic scale model
KW - Thermal mixing
UR - http://www.scopus.com/inward/record.url?scp=85211195291&partnerID=8YFLogxK
U2 - 10.1016/j.nucengdes.2024.113746
DO - 10.1016/j.nucengdes.2024.113746
M3 - Article
AN - SCOPUS:85211195291
SN - 0029-5493
VL - 432
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 113746
ER -