| 超临界水堆全系统启动特性研究 |
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| 引用本文： | 袁园,单建强,王丽,王冬青,张小英.超临界水堆全系统启动特性研究[J].核动力工程,2019,40(5):13-17. |
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| 作者姓名： | 袁园 单建强 王丽 王冬青 张小英 |
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| 作者单位： | 中山大学中法核工程与技术学院,广东珠海,519080;西安交通大学核科学与技术学院,西安,710049 |
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| 摘 要： | 为研究超临界水堆（SCWR）全系统启动特性，以SCTRAN程序为计算工具，基于中国超临界水堆（CSR1000）堆芯参数、高性能轻水反应堆（HPLWR）热力循环回路和日本SCWR再循环启动回路，建立了SCWR完整再循环启动系统模型。通过与HPLWR热力循环回路的稳态参数对比，验证了完整回路模型的正确性。分析在控制系统控制下的CSR1000再循环启动过程，得到了启动过程中堆芯、汽鼓、汽轮机、各级抽汽、再热器、各级回热器的瞬态响应曲线。计算结果表明，启动序列和启动过程各热工参数的变化符合预期，系统稳定启动；堆芯始终处于单相状态；汽轮机入口为超临界蒸汽；经过高压和低压回热器后堆芯入口温度能够达到280℃；高压缸入口压力维持恒定；在启动的过程中最大燃料包壳表面温度低于限值温度650℃，整个启动过程安全可靠。
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| 关 键 词： | 超临界水堆 SCTRAN 全系统启动模型 |
Study on Thermal Hydraulic Characteristics in Startup of SCWR |
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| Abstract: | To investigate the startup characteristics of whole supercritical pressure water cooled reactor (SCWR) system, the complete startup system model of the SCWR was established with the analysis code SCTRAN, based on the CSR1000 core, high performance light water reactor (HPLWR) steam cycle and SCWR circulation startup loop. The correctness of the model was verified in comparison with the steady-state parameters of the steam cycle of the HPLWR. A sliding pressure startup procedure with the circulation loop that employs a control system was analyzed, and the transient performances of the core, steam drum, steam turbine, reheaters, steam extraction, and heaters at each stage were obtained. The calculation results show that the startup sequence and startup thermal parameters agree well with the expectation: the system starts up stably and the core remains in the single phase; the inlet steam of the turbine stays supercritical; the core inlet temperature can reach 280℃ after the high-pressure and low-pressure heaters; the inlet pressure of the high-pressure turbine can be kept constant. During the startup procedure, the maximum cladding surface temperature remains below the limit temperature of 650℃. The entire startup procedure is safe and reliable. |
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