为评估系统的性能，进行了中子学和热工水力学计算。
Neutronics and thermal hydraulics calculation were performed to estimate the performance of the whole system.
试验是为确定自然循环池式核供热堆的热工水力学参数而进行的。
The purpose of this experiment was to determine the themohydraulic parameters in pool-type nuclear heating reactor with natural circulation.
建立了套管管束式换热器的计算模型，以便进行该种换热器热工水力学设计计算和结构优化。
An analytical model of thermal-hydraulic design and structural optimization was developed for a double-tube bundle heat exchanger of an integrated nuclear reactor.
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