TY - JOUR
T1 - TOPAZ-Ⅱ反应堆堆芯的稳态热工代理模型
AU - Liao, Ruian
AU - Wang, Xuesong
AU - Qi, Lin
AU - Zhang, Dalin
AU - Tian, Wenxi
AU - Su, Guanghui
AU - Qiu, Suizheng
N1 - Publisher Copyright:
© 2025 Atomic Energy Press. All rights reserved.
PY - 2025/6
Y1 - 2025/6
N2 - The TOPAZ-Ⅱ reactor, a space nuclear reactor power designed by the former Soviet Union, uses sodium-potassium alloy (NaK-78) as coolant and adopts thermionic conversion power generation principle to provide power for the load. To quickly and accurately calculate the steady state thermal parameters of the core, a steady state high-precision thermal surrogate model of the core was established. This study firstly used Fluent to carry out thermal calculation of core steady state, with grid node temperatures along the central longitudinal cross-section selected as sample data. Then the main features in samples were extracted by Proper Orthogonal Decomposition (POD) method, and the top 10 modes were retained based on 99.999% energy proportion for model order reduction. Finally, through Back Propagation (BP) neural network, the steady state thermal surrogate model of core was established and was compared and validated with Fluent. The results show that the maximum error of the surrogate model in calculating the temperature at grid nodes is 9.95 K, the relative error is less than 1% and the calculation time is less than 1 s. Taking the outlet temperature of the hottest coolant channel as a reference, the flow-power percentage ratio of the coolant to maintain the single-phase working state should be greater than 0.35 calculated by the thermal surrogate model. Therefore, the thermal surrogate model established in this paper can quickly and accurately calculate the steady state thermal parameters of the core, achieve simulation prediction of the core, and provide certain reference for the thermal safety analysis of the core.
AB - The TOPAZ-Ⅱ reactor, a space nuclear reactor power designed by the former Soviet Union, uses sodium-potassium alloy (NaK-78) as coolant and adopts thermionic conversion power generation principle to provide power for the load. To quickly and accurately calculate the steady state thermal parameters of the core, a steady state high-precision thermal surrogate model of the core was established. This study firstly used Fluent to carry out thermal calculation of core steady state, with grid node temperatures along the central longitudinal cross-section selected as sample data. Then the main features in samples were extracted by Proper Orthogonal Decomposition (POD) method, and the top 10 modes were retained based on 99.999% energy proportion for model order reduction. Finally, through Back Propagation (BP) neural network, the steady state thermal surrogate model of core was established and was compared and validated with Fluent. The results show that the maximum error of the surrogate model in calculating the temperature at grid nodes is 9.95 K, the relative error is less than 1% and the calculation time is less than 1 s. Taking the outlet temperature of the hottest coolant channel as a reference, the flow-power percentage ratio of the coolant to maintain the single-phase working state should be greater than 0.35 calculated by the thermal surrogate model. Therefore, the thermal surrogate model established in this paper can quickly and accurately calculate the steady state thermal parameters of the core, achieve simulation prediction of the core, and provide certain reference for the thermal safety analysis of the core.
KW - Back propagation (BP) neural network
KW - Proper orthogonal decomposition (POD)
KW - TOPAZ-Ⅱ reactor
KW - Thermal surrogate model
UR - https://www.scopus.com/pages/publications/105008582679
U2 - 10.13832/j.jnpe.2024.070011
DO - 10.13832/j.jnpe.2024.070011
M3 - 文章
AN - SCOPUS:105008582679
SN - 0258-0926
VL - 46
SP - 24
EP - 33
JO - Hedongli Gongcheng/Nuclear Power Engineering
JF - Hedongli Gongcheng/Nuclear Power Engineering
IS - 3
ER -