2022
DOI: 10.1016/j.energy.2022.124976
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Multi-objective optimization of helical coil steam generator in high temperature gas reactors with genetic algorithm and response surface method

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Cited by 31 publications
(6 citation statements)
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References 49 publications
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“…It is also employed for designing and simulating safe and effective fuel-loading patterns in nuclear reactors (Zhao et al, 1998). Further, the GA is utilized for designing efficient radiation shielding in SMR (Bagheri and Khalafi, 2023), development of an optimized thermodynamic model in a VVER-1200 reactor (Khan et al, 2022), optimal energy management in the HTGR (Sun J. et al, 2022), optimization of fuel loading pattern in the experimental fast reactor (Lima-Reinaldo and François, 2023), in-core fuel…”
Section: Genetic Algorithmmentioning
confidence: 99%
“…It is also employed for designing and simulating safe and effective fuel-loading patterns in nuclear reactors (Zhao et al, 1998). Further, the GA is utilized for designing efficient radiation shielding in SMR (Bagheri and Khalafi, 2023), development of an optimized thermodynamic model in a VVER-1200 reactor (Khan et al, 2022), optimal energy management in the HTGR (Sun J. et al, 2022), optimization of fuel loading pattern in the experimental fast reactor (Lima-Reinaldo and François, 2023), in-core fuel…”
Section: Genetic Algorithmmentioning
confidence: 99%
“…[163] composed the coolant flow path in detail and improved the original thermal analysis model of HTR-10 built under the THERMIX program. [164] used the finite difference method (FDM) and response surface method (RSM) for thermal modeling to achieve multi-objective optimization of a spiral tube steam generator.…”
Section: B Modelingmentioning
confidence: 99%
“…[179] used the MPC method based on DMC for supervisory control of NSSS to regulate the NSSS thermal power by adjusting the neutron flux, coolant flow rate, and other set values. Some evolutionary computational algorithms, such as genetic algorithms (GA) [164], can be applied for parameter optimization of HTGR.…”
Section: Control Strategymentioning
confidence: 99%
“…Subsequently, Germany successively built two pebble-bed nuclear plants, a 45 MWth test HTGR (AVR) and a 750 MWth HTGR power plant (THTR-300) [8]. THTR-300 utilized a once-though helical coil bundle for its steam generator [10]. The latest HTGRs that utilize a once-through helical coil steam generator are HTR-10 and HTR-PM from China [7][8].…”
Section: Introduction mentioning
confidence: 99%