首页> 美国政府科技报告 >Extension of the Supercritical Carbon Dioxide Brayton Cycle to Low Reactor Power Operation: Investigations Using the Coupled ANL Plant Dynamics Code-SAS4A/SASSYS-1 Liquid Metal Reactor Code System.
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Extension of the Supercritical Carbon Dioxide Brayton Cycle to Low Reactor Power Operation: Investigations Using the Coupled ANL Plant Dynamics Code-SAS4A/SASSYS-1 Liquid Metal Reactor Code System.

机译:将超临界二氧化碳布雷顿循环扩展到低反应堆功率运行:使用耦合aNL工厂动力学代码-sas4a / sassYs-1液态金属反应堆代码系统进行调查。

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Significant progress has been made on the development of a control strategy for the supercritical carbon dioxide (S-CO(sub 2)) Brayton cycle enabling removal of power from an autonomous load following Sodium-Cooled Fast Reactor (SFR) down to decay heat levels such that the S-CO(sub 2) cycle can be used to cool the reactor until decay heat can be removed by the normal shutdown heat removal system or a passive decay heat removal system such as Direct Reactor Auxiliary Cooling System (DRACS) loops with DRACS in-vessel heat exchangers. This capability of the new control strategy eliminates the need for use of a separate shutdown heat removal system which might also use supercritical CO(sub 2). It has been found that this capability can be achieved by introducing a new control mechanism involving shaft speed control for the common shaft joining the turbine and two compressors following reduction of the load demand from the electrical grid to zero. Following disconnection of the generator from the electrical grid, heat is removed from the intermediate sodium circuit through the sodium-to-CO(sub 2) heat exchanger, the turbine solely drives the two compressors, and heat is rejected from the cycle through the CO(sub 2)-to-water cooler. To investigate the effectiveness of shaft speed control, calculations are carried out using the coupled Plant Dynamics Code-SAS4A/SASSYS-1 code for a linear load reduction transient for a 1000 MWt metallic-fueled SFR with autonomous load following. No deliberate motion of control rods or adjustment of sodium pump speeds is assumed to take place. It is assumed that the S-CO(sub 2) turbomachinery shaft speed linearly decreases from 100 to 20% nominal following reduction of grid load to zero. The reactor power is calculated to autonomously decrease down to 3% nominal providing a lengthy window in time for the switchover to the normal shutdown heat removal system or for a passive decay heat removal system to become effective.

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