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首页> 外文期刊>Annals of nuclear energy >Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system
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Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor system

机译:小型模块化高温气冷堆系统紧凑布雷顿循环性能的初步研究

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摘要

A High Temperature Gas-cooled Reactor (HTGR) system was generally designed and planned to be constructed in a medium size reactor (around 600 MWe power output) in the past. In this paper, authors are exploring the potential of very small modular type HTGR with a special attention given to the power conversion system. Since HTGR is relatively less challenging to achieve passive safety while easy to adopt an air-cooled Brayton cycle for a power conversion system, HTGR can be suitable for a small modular reactor application. However, as the size of the power system decreases the consisting component performance usually degrades and the final effect on the total system performance was not seriously studied before for a small size HTGR system. 20 MWth reactor was chosen for this study to investigate how helium Brayton cycle performance can be affected by the component level performance and how the optimal operating condition shifts when the system size reduces. The discussion of component design that can deliver assumed performance for the cycle estimation will be briefly presented as well. Furthermore, a supercritical CO_2 cycle option will be compared to the helium Brayton cycle to show that the S-CO_2 cycle can be a good alternative for a very small scale system.
机译:通常设计和计划在过去的中型反应堆(功率输出约为600 MWe)中建造高温气冷堆(HTGR)系统。在本文中,作者正在研究非常小型的模块化HTGR的潜力,并特别关注功率转换系统。由于HTGR在实现被动安全性方面相对较少挑战,同时易于将空冷式布雷顿循环用于功率转换系统,因此HTGR可适用于小型模块化反应堆应用。但是,随着电力系统尺寸的减小,组成组件的性能通常会下降,并且对于小型HTGR系统,对整体系统性能的最终影响以前并未得到认真研究。本研究选择了20兆瓦时反应堆,以研究组件级性能如何影响布雷顿河氦循环性能,以及当系统尺寸减小时最佳运行条件如何变化。还将简要介绍可以为循环估计提供预期性能的组件设计。此外,将超临界CO_2循环选项与氦布雷顿循环进行比较,以表明S-CO_2循环对于超小型系统可以是一个很好的选择。

著录项

  • 来源
    《Annals of nuclear energy》 |2015年第1期|11-19|共9页
  • 作者单位

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon 305-701, Republic of Korea;

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon 305-701, Republic of Korea;

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon 305-701, Republic of Korea;

    Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong Yuseong-gu, Daejeon 305-701, Republic of Korea;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    High Temperature Gas-cooled Reactor; (HTGR); Small Modular Reactor (SMR); Helium Brayton cycle; Supercritical Carbon Dioxide (S-CO_2); Brayton cycle; Turbornachinery;

    机译:高温气冷堆(HTGR);小型模块化反应堆(SMR);氦布雷顿循环超临界二氧化碳(S-CO_2);布雷顿循环涡轮机械;

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