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- [4] Validation and Typical Application of Thermal-hydraulic Code Analysis in Numerical Reactor with CVR-PACA Code Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (09): : 1569 - 1580
- [7] Development and Preliminary Validation of Three-dimensional Subchannel Thermal-hydraulic Analysis Code CorTAF for Numerical Reactor Core Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (02): : 261 - 270
- [8] Numerical simulation analysis of the thermal-hydraulic behavior of the HPR1000 containment based on integral TH behaviour of containment experiment Harbin Gongcheng Daxue Xuebao/Journal of Harbin Engineering University, 2023, 44 (07): : 1156 - 1161and1174