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首页> 外文学位 >Conceptual design of a thermalhydraulic loop for multiple test geometries at supercritical conditions named Supercritical Phenomena Experimental Test Apparatus (SPETA).
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Conceptual design of a thermalhydraulic loop for multiple test geometries at supercritical conditions named Supercritical Phenomena Experimental Test Apparatus (SPETA).

机译：在超临界条件下用于多种测试几何形状的热工液压回路的概念设计，称为超临界现象实验测试装置（SPETA）。

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摘要

The efficiency of nuclear reactors can be improved by increasing the operating pressure of current nuclear reactors. Current CANDU-type nuclear reactors use heavy water as coolant at an outlet pressure of up to 11.5 MPa. Conceptual SuperCritical Water Reactors (SCWRs) will operate at a higher coolant outlet pressure of 25 MPa. Supercritical water technology has been used in advanced coal plants and its application proves promising to be employed in nuclear reactors. To better understand how supercritical water technology can be applied in nuclear power plants, supercritical water loops are used to study the heat transfer phenomena as it applies to CANDU-type reactors.;Operating limits for SPETA have been established to be able to capture the important heat transfer phenomena at supercritical conditions. Heat balance and flow calculations have been done to appropriately size components in the loop. Sensitivity analysis has been done to find the optimum design for the loop.;A conceptual design of a loop known as the Supercritical Phenomena Experimental Apparatus (SPETA) has been done. This loop has been designed to fit in a 9 m by 2 m by 2.8 m enclosure that will be installed at the University of Ontario Institute of Technology Energy Research Laboratory. The loop include components to safely start up and shut down various test sections, produce a heat source to the test section, and to remove reject heat. It is expected that loop will be able to investigate the behaviour of supercritical water in various geometries including bare tubes, annulus tubes, and multi-element-type bundles. The experimental geometries are designed to match the fluid properties of Canadian SCWR fuel channel designs so that they are representative of a practical application of supercritical water technology in nuclear plants. This loop will investigate various test section orientations which are the horizontal, vertical, and inclined to investigate buoyancy effects. Frictional pressure drop effects and satisfactory methods of estimating hydraulic resistances in supercritical fluid shall also be estimated with the loop.
机译：可以通过增加当前核反应堆的运行压力来提高核反应堆的效率。当前的CANDU型核反应堆使用重水作为冷却剂，出口压力高达11.5 MPa。概念超临界水反应堆（SCWR）将在更高的冷却液出口压力25 MPa下运行。超临界水技术已用于先进的燃煤电厂，其应用证明有望在核反应堆中使用。为了更好地理解超临界水技术如何应用​​于核电站，超临界水回路被用于研究应用于CANDU型反应堆的传热现象。；已经确定了SPETA的运行极限，以便能够捕获重要的超临界条件下的热传递现象。已经进行了热平衡和流量计算，以适当调整回路中的组件尺寸。进行了灵敏度分析，以找到用于环路的最佳设计。已完成了称为超临界现象实验设备（SPETA）的环路的概念设计。该环路设计为可安装在9m x 2 m x 2.8 m的外壳中，该外壳将安装在安大略大学技术学院能源研究实验室。回路中的组件可安全地启动和关闭各个测试部分，为测试部分提供热源，并去除废热。可以预期，环路将能够研究各种几何形状中的超临界水的行为，包括裸露的管，环管和多元素类型的管束。设计实验几何形状以匹配加拿大SCWR燃料通道设计的流体特性，因此它们代表了超临界水技术在核电站中的实际应用。该循环将研究各种测试截面的方向，包括水平，垂直和倾斜方向，以研究浮力效果。还应通过回路估算摩擦压降效应和估算超临界流体中水力阻力的令人满意的方法。

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  • 作者

    Adenariwo, Adepoju.;

  • 作者单位

    University of Ontario Institute of Technology (Canada).;

  • 授予单位 University of Ontario Institute of Technology (Canada).;
  • 学科 Engineering Nuclear.
  • 学位 M.A.Sc.
  • 年度 2012
  • 页码 226 p.
  • 总页数 226
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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