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Thermal and stability considerations for a supercritical water-cooled fast reactor with downward-flow channels during power-raising phase of plant startup

机译:在工厂启动的功率提升阶段中具有向下流动通道的超临界水冷快堆的热和稳定性考虑

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摘要

This paper describes study on the procedure of raising the reactor thermal power and the reactor coolant flow rate during the power-raising phase of plant startup for the supercritical water-cooled fast reactor (SWFR), which is selected as one of the Generation IV reactor concepts. Since part of the seed fuel assemblies and all the blanket fuel assemblies of the SWFR are cooled by downward flow, the feedwater from the reactor vessel inlet nozzle to the mixing plenum located below the core is distributed among these fuel assemblies and the downcomer. The flow rate distribution as the function of both the reactor thermal power and the feedwater flow rate, which are the design parameters for the power-raising phase, is obtained by the thermal hydraulic calculations. Based on the flow rate distribution, thermal analyses and thermal-hydraulic stability analyses are carried out in order to obtain the available region of the reactor thermal power and the feedwater flow rate for the power-raising phase. The criteria for the "available" region are the maximum cladding surface temperature (MCST) and the decay ratio of thermal-hydraulic stability in three "hot" channels; two seed assemblies with upward/downward flow and a blanket assembly. The effects of various heat transfer correlations and axial power distributions are also studied.
机译:本文介绍了选择超临界水冷快堆(SWFR)的工厂启动发电阶段中提高反应堆热功率和反应堆冷却剂流速的程序的研究,该反应堆被选为第四代反应堆之一概念。由于SWFR的部分种子燃料组件和所有毯式燃料组件均通过向下流动进行冷却,因此,从反应堆容器入口喷嘴到位于堆芯下方的混合气室的给水在这些燃料组件和降液管之间分配。通过热力水力计算获得流量分布,该流量分布是反应堆热功率和给水流量的函数,它们是功率提升阶段的设计参数。基于流量分布,进行热分析和热水稳定性分析,以获得反应堆热功率的可用区域和功率提升阶段的给水流量。 “可用”区域的标准是最高包层表面温度(MCST)和三个“热”通道中热工水力稳定性的衰减率;两个具有向上/向下流动的种子组件和一个毯子组件。还研究了各种传热相关性和轴向功率分布的影响。

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  • 来源
    《Nuclear Engineering and Design》 |2009年第4期|665-679|共15页
  • 作者单位

    Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Yayoi, Bunkyo-ku, Tokyo 113-8656, Japan;

    Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Yayoi, Bunkyo-ku, Tokyo 113-8656, Japan;

    Nuclear Professional School School of Engineering, The University of Tokyo, Tokai-mura, Ibaraki 319-1188, Japan;

    Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, Yayoi, Bunkyo-ku, Tokyo 113-8656, Japan Nuclear Professional School School of Engineering, The University of Tokyo, Tokai-mura, Ibaraki 319-1188, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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