NUCLEAR TECHNIQUES, Volume. 48, Issue 6, 060013(2025)
Transient simulation of nuclear thermal-hydraulic coupling startup of heat pipe reactor based on reduced-order models
Fig. 1. Diagram of neutron calculation model of MegaPower heat pipe reactor (color online)
Fig. 2. Schematics of 2D heat transfer calculation model of MegaPower heat pipe reactor (color online)
Fig. 3. Diagram of mechanical calculation model of MegaPower heat pipe reactor
Fig. 4. The coupling relationship between multiple physical fields in a heat pipe stack
Fig. 5. Comparison of power distribution prediction between POD-RBF model and high-resolution model (color online)
Fig. 6. Histogram of power prediction errors between POD-RBF model and high-resolution model
Fig. 8. Temperature variation curves during low-power startup (color online)
Fig. 9. Variation curves of control drum angle and reactivity during low-power startup (color online)
Fig. 10. Temperature variation curves during power adjustment to nominal level (color online)
Fig. 11. Curves of control drum angle and reactivity over time during power adjustment to nominal level (color online)
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Shuqiu SHEN, Jinbiao XIONG, Xiaojing LIU, Tengfei ZHANG. Transient simulation of nuclear thermal-hydraulic coupling startup of heat pipe reactor based on reduced-order models[J]. NUCLEAR TECHNIQUES, 2025, 48(6): 060013
Category: Special Topics of Academic Papers at The 27th Annual Meeting of the China Association for Science and Technology
Received: Nov. 22, 2024
Accepted: --
Published Online: Jul. 25, 2025
The Author Email: Tengfei ZHANG (张滕飞)