为了确保超临界二氧化碳再压缩布雷顿循环直接冷却核能系统在变负荷工况下的安全经济运行,利用稳态和瞬态回热器换热实验验证了自主研发的瞬态分析程序SCTRAN/CO
2
在预测布雷顿循环动态特性方面的可行性,并以该程序作为分析工具,开展了超临界二氧化碳再压缩布雷顿循环核能系统分别在反应堆反应性扰动和二次侧冷却水流量扰动两种典型瞬态工况下的开环动态特性研究,开发了主压缩机入口温度恒定、堆芯出口温度恒定及改变循环工质装量的负荷运行策略,研究了系统在100%~50%~100%变负荷工况下的瞬态响应。结果表明,装量控制策略能实现以额定满功率5%/min的速率追踪负荷,并保证系统安全经济运行。此过程中,堆芯压力波动0.6 MPa
堆芯出口温度波动不超过5℃。研究获得的瞬态分析工具、开环特性和控制策略为此核能系统的负荷运行策略研究提供了参考。
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