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A Thermal-fluid Assessment Of A Cooled-vessel Concept For A Vhtr

机译:Vhtr的冷却容器概念的热流体评估

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摘要

Flow distribution and thermal analyses of a conceptual design of a cooled vessel for a very high temperature reactor (VHTR), which has a forced vessel cooling with an internal coolant path through a permanent side reflector, have been performed. A computational fluid dynamics (CFD) code was employed to investigate flow distributions at inlet and upper plenums of the proposed cooled-vessel concept. Thermal-fluid analyses of the cooled vessel during a normal operation were carried out by using the CFD code with the boundary conditions provided by the GAMMA system analysis code. The transient analyses during postulated accidents were conducted by the GAMMA code itself. According to the results, the flow deviation at the riser holes due to a change of the inlet flow path to the core inlet is about ±20% which results in about a 3-7% core flow deviation from the average value depending on the upper plenum height. The pressure drops in the inlet and upper plenums are estimated to be from 13 to 25 kPa with a change of the upper plenum height. A cooling flow of more than 4 kg/s is sufficient to maintain the RPV temperature within the required limit during a normal operation. Transient analysis reveals that the reactor vessel is exposed to a temperature above its limit of 371 ℃ but this duration is shorter than the allowable time for a creep region with a sufficient safety margin. The results suggest that the cooled-vessel concept considered in this paper has the potential to be used for a VHTR but further and more detailed studies are required to realize the proposed concept.
机译:进行了高温反应堆(VHTR)冷却容器的概念设计的流量分布和热分析,该反应堆具有强制冷却的容器,并带有通过永久性侧面反射器的内部冷却剂路径。计算流体动力学(CFD)代码用于研究所提出的冷却容器概念的入口和上部气室的流量分布。通过使用CFD代码以及GAMMA系统分析代码提供的边界条件,对正常运行期间的冷却容器进行了热流体分析。假定事故期间的瞬态分析由GAMMA规范本身进行。根据结果​​,由于流入岩心入口的入口流路的变化而导致的冒口孔处的流量偏差约为±20%,这导致岩心流量偏离平均值的3-7%,具体取决于上限气室高度。进气口和上气室的压降估计为13至25 kPa,随上气室高度的变化而变化。大于4 kg / s的冷却流量足以在正常运行期间将RPV温度保持在所需的限制内。瞬态分析表明,反应堆容器暴露在高于其极限温度371℃的温度下,但该持续时间短于具有足够安全裕度的蠕变区域的允许时间。结果表明,本文中考虑的冷却容器概念具有用于VHTR的潜力,但需要进一步更详细的研究来实现所提出的概念。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2008年第12期|p.3360-3369|共10页
  • 作者单位

    Korea Atomic Energy Research Institute, 1045 Daedeokdaero, Yoseong, Daejeon 304-353, South Korea;

  • 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 原子能技术;
  • 关键词

  • 入库时间 2022-08-18 00:45:41

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