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Dynamic analysis code development for space nuclear power systems
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AI
DOI：10.1016/j.pnucene.2024.105601.png)
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摘要
En 中文
Space nuclear power systems (SNPs) are considered an optimal power solution for future space missions. Among various system designs, a gas-cooled reactor coupled with closed Brayton cycle energy conversion systems has emerged as one of the most promising options for generating electrical power in the range of hundreds to thousands of kilowatts. Due to strong parameter coupling, small design margins, and limited control strategies, a reliable and accurate dynamic analysis tool is essential for the optimization and operation safety of SNPs. In this paper, RELAP5 is modified to support the dynamic analysis of these systems, following a comparison between the original code capabilities and the simulation requirements for SNPs. A compressor model and a turbine model are developed, and the heat transfer model is adapted for compact counterflow heat exchangers. Additionally, the convective and radiation heat transfer models are modified for open lattice reactors with compact rod bundles. The accuracy of the modified RELAP5 is verified through comparisons with results from the system design code Megrez, the CFD simulations and the JIMO reports. The results confirm that the dynamic analysis code developed in this paper is suitable for transient analysis of SNPs.
Keyword:
Space nuclear power system
Gas-cooled reactor
Closed Brayton cycle
Dynamic analysis
RELAP5
期刊
IF:
3.2
论文数:
5.7K
被引数:
1.1W
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