NUCLEAR TECHNIQUES, Volume. 47, Issue 11, 110604(2024)
Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics
Fig. 1. Comparison of experiment values and simulation values under different working conditions
Fig. 2. Framework of neutronics-material-thermal-hydraulics coupling
Fig. 5. Dynamic changes of key coupling parameters over time under standard operating condition (a) Average thickness, (b) Maximum thickness, (c) Average removal thickness, (d) Average temperature, (e) Maximum temperature, (f) kinf
Fig. 6. Distribution contours of thickness of the oxide layers under standard operating condition (a) Thickness contour of magnetite layer, (b) Thickness contourof Fe-Cr spinel layer
Fig. 7. Dynamic changes of key coupling parameters over time under different oxygen concentrations (a) Average thickness,(b) Maximum thickness, (c) Average removal thickness, (d) Average temperature, (e) Maximum temperature, (f) kinf
Fig. 8. Distribution contours of thickness of the oxide layers for 10 000 h under different oxygen concentrations (a) Thickness contour of magnetite layer, (b) Thickness contour of Fe-Cr spinel layer
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Xu JI, Xiang CHAI, Lefu ZHANG, Xiaojing LIU. Neutronics-thermal-hydraulics-material coupling study of lead-bismuth cooled reactor single rod based on oxidative corrosion characteristics[J]. NUCLEAR TECHNIQUES, 2024, 47(11): 110604
Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING
Received: Nov. 29, 2023
Accepted: --
Published Online: Jan. 2, 2025
The Author Email: Xiaojing LIU (LIUXiaojing)