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The Code for Integrated Thermal-Hydraulics and Reactor Analysis (CITHARA) is a best-estimate thermal–hydraulic system analysis program developed jointly by China Nuclear Power Engineering Co., Ltd. (CNNC) and Shanghai Jiao Tong University, with independent intellectual property rights. It can be used for transient and accident analysis of nuclear power plants, achieving integrated modelling, calculation, and analysis that includes the reactor core, primary and secondary loops, safety systems, and containment. The program can model pressurized water reactor nuclear power plants and perform computational analysis of transient and accident processes, including normal operation and operational transients (Condition I), as well as various events and accidents (Conditions II, III, IV). HPR1000 is an advanced mega-kilowatt-class third-generation pressurized water reactor (PWR) nuclear power technology developed by China, based on more than 30 years of experience in the scientific research, design, equipment manufacturing, construction, and operation of nuclear power. HPR1000 introduces the concept of a combined active and passive safety design, which reflects the idea of integrated safety and balanced design. HPR1000 and its subsequent models are third-generation pressurized water reactor nuclear power technologies designed with complete independent intellectual property rights. Taking the above into account, AHPR1000 was developed as an upgraded and innovative model based on HPR1000 by the CNNC, which aims to provide a mainstream clean energy solution around the year 2030. AHPR1000 develops three major passive safety systems to deal with design basic accidents and a set of active systems with minimal power supply. This paper establishes a thermal–hydraulic analysis model for the three-loop power plant of the APHR1000 based on the CITHARA program, conducts steady-state calculations, and compares critical parameters with the RELAP5 calculation results and the power plant design values. Based on the steady-state CITHARA-RELAP5 verification results, it is shown that the CITHARA program can perform simulation calculations and analyses for the APHR1000 three-loop power plant, with minimal deviations in the calculation results. A single-pump loss-of-flow accident simulation is conducted to verify the effectiveness of the CITHARA program in accident simulation.

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Numerical Simulation of AHPR1000’s Thermal–Hydraulic Model Based on CITHARA Code

  • 会议论文

  • 发表日期：

    2026年

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  • Geng Yiwa,
  • Ma Mingjie,
  • Fang Jun,
  • Liu Jiatai

摘要

The Code for Integrated Thermal-Hydraulics and Reactor Analysis (CITHARA) is a best-estimate thermal–hydraulic system analysis program developed jointly by China Nuclear Power Engineering Co., Ltd. (CNNC) and Shanghai Jiao Tong University, with independent intellectual property rights. It can be used for transient and accident analysis of nuclear power plants, achieving integrated modelling, calculation, and analysis that includes the reactor core, primary and secondary loops, safety systems, and containment. The program can model pressurized water reactor nuclear power plants and perform computational analysis of transient and accident processes, including normal operation and operational transients (Condition I), as well as various events and accidents (Conditions II, III, IV). HPR1000 is an advanced mega-kilowatt-class third-generation pressurized water reactor (PWR) nuclear power technology developed by China, based on more than 30 years of experience in the scientific research, design, equipment manufacturing, construction, and operation of nuclear power. HPR1000 introduces the concept of a combined active and passive safety design, which reflects the idea of integrated safety and balanced design. HPR1000 and its subsequent models are third-generation pressurized water reactor nuclear power technologies designed with complete independent intellectual property rights. Taking the above into account, AHPR1000 was developed as an upgraded and innovative model based on HPR1000 by the CNNC, which aims to provide a mainstream clean energy solution around the year 2030. AHPR1000 develops three major passive safety systems to deal with design basic accidents and a set of active systems with minimal power supply. This paper establishes a thermal–hydraulic analysis model for the three-loop power plant of the APHR1000 based on the CITHARA program, conducts steady-state calculations, and compares critical parameters with the RELAP5 calculation results and the power plant design values. Based on the steady-state CITHARA-RELAP5 verification results, it is shown that the CITHARA program can perform simulation calculations and analyses for the APHR1000 three-loop power plant, with minimal deviations in the calculation results. A single-pump loss-of-flow accident simulation is conducted to verify the effectiveness of the CITHARA program in accident simulation.