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BRAYTON CYCLE FOR HIGH-TEMPERATURE GAS-COOLED REACTORS

机译:高温气冷反应器的布雷顿循环

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摘要

This paper describes research on improving the Bray-ton cycle efficiency for a high-temperature gas-cooled reactor (HTGR). In this study, we are investigating the efficiency of an indirect helium Brayton cycle for the power conversion side of an HTGR power plant. A reference case based on a 250-MW(thermal) pebble bed HTGR was developed using helium gas as a working fluid in both the primary and power conversion sides. The commercial computer code HYSYS was used for process optimization. A numerical model using the Visual-Basic (V-B) computer language was also developed to assist in the evaluation of the Brayton cycle efficiency. Results from both the HYSYS simulation and the V-B model were compared with Japanese calculations based on the 300-MW(electric) Gas Turbine High-Temperature Reactor (GTHTR) that was developed by the Japan Atomic Energy Research Institute. After benchmarking our models, parametric investigations were performed to see the effect of important parameters on the cycle efficiency. We also investigated single-shaft versus multiple-shaft arrangements for the turbomachinery. The results from this study are applicable to other reactor concepts such as fast gas-cooled reactors, supercritical water reactors, and others. The ultimate goal of this study is to use other fluids such as supercritical carbon dioxide for the HTGR power conversion loop in order to improve the cycle efficiency over that of the helium Brayton cycle. This study is in progress, and the results will be published in a subsequent paper.
机译:本文介绍了改善高温气冷堆(HTGR)布雷顿循环效率的研究。在这项研究中,我们正在研究HTGR电厂的功率转换侧间接氦布雷顿循环的效率。开发了一个基于250兆瓦(热)卵石床HTGR的参考案例,在一次和功率转换侧均使用氦气作为工作流体。商业计算机代码HYSYS用于过程优化。还开发了使用Visual Basic(V-B)计算机语言的数值模型,以帮助评估Brayton循环效率。 HYSYS模拟和V-B模型的结果都与日本基于日本原子能研究所开发的300兆瓦(电)燃气轮机高温反应堆(GTHTR)的计算结果进行了比较。在对我们的模型进行基准测试之后,进行了参数研究,以了解重要参数对循环效率的影响。我们还研究了涡轮机械的单轴与多轴布置。这项研究的结果适用于其他反应堆概念,例如快速气冷反应堆,超临界水反应堆等。这项研究的最终目标是将其他流体(例如超临界二氧化碳)用于HTGR功率转换回路,以提高氦氦布雷顿循环的循环效率。这项研究正在进行中,其结果将在随后的论文中发表。

著录项

  • 来源
    《Nuclear Technology》 |2005年第3期|p.324-336|共13页
  • 作者

    CHANG H. OH; RICHARD L. MOORE;

  • 作者单位

    Idaho National Engineering and Environmental Laboratory, Thermal Fluids Department 2525 N. Fremont Avenue, Idaho Falls, Idaho 83415-3885;

  • 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

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