首页> 外文会议>International topical meeting on nuclear plant instrumentation, control, and human-machine interface technologies >SUPERCRITICAL CARBON DIOXIDE BRAYTON CYCLE CONTROL FOR A NUCLEAR POWER PLANT: LOAD FOLLOWING AND DECAY HEAT REMOVAL
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SUPERCRITICAL CARBON DIOXIDE BRAYTON CYCLE CONTROL FOR A NUCLEAR POWER PLANT: LOAD FOLLOWING AND DECAY HEAT REMOVAL

机译:核电站的超临界二氧化碳布雷顿循环控制:负荷跟踪和除热

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The supercritical carbon dioxide (S-CO_2) Brayton cycle offers efficiency and economic benefits as a power converter for advanced reactors by taking advantage of the property variation behavior of supercritical CO_2 near the critical point. That particular property variation behavior at the same time presents challenges for cycle control and transient analysis. The Plant Dynamics Code (PDC) has been developed at ANL to address these challenges and to provide an analysis to develop a control strategy for the cycle. The PDC has been coupled to the SAS4A/SASSYS-1 Liquid Metal Reactor analysis code system for the analysis of liquid metal-cooled reactors, such as Sodium Cooled Fast Reactors (SFRs). A SFR plant under load following and transition to the decay heat removal mode is analyzed with the PDC and SAS4A/SASSYS-1. The S-CO_2 cycle and reactor controllers are optimized to achieve a favorable system response at all stages, as demonstrated by the transient simulation of the plant. The S-CO_2 cycle is shown to be capable of operating from 100% power to as low as at least 1% reactor power in the decay heat removal mode.
机译:通过利用超临界CO_2在临界点附近的特性变化行为,超临界二氧化碳(S-CO_2)布雷顿循环作为先进反应堆的功率转换器,可提供效率和经济效益。同时,特定的特性变化行为对周期控制和瞬态分析提出了挑战。 ANL已制定了《工厂动力学规范》(PDC),以应对这些挑战并提供分析以制定该周期的控制策略。 PDC已与SAS4A / SASSYS-1液态金属反应堆分析代码系统耦合,用于分析液态金属冷却的反应堆,例如钠冷快堆(SFR)。使用PDC和SAS4A / SASSYS-1分析了处于负载跟踪并过渡到衰减除热模式的SFR工厂。如工厂的瞬态仿真所示,对S-CO_2循环和反应器控制器进行了优化,以在所有阶段均实现良好的系统响应。已显示出S-CO_2循环能够在衰减除热模式下从100%的功率运行至低至至少1%的反应堆功率。

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