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Modeling and control of nuclear reactor cores for electricity generation: A review of advanced technologies

机译:发电用核反应堆堆芯的建模与控制:先进技术综述

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摘要

This investigation is to review advanced technologies for modeling and control of reactor cores in nuclear power plants for electricity generation. A reactor core in a nuclear power plant is the key part as the hot source with radioactivity nuclear fuel, which possesses security risks and economic potential. Incapacity of a nuclear power plant to carry out desired control of its core can result in either higher operating costs or a reduction in system security and reliability, and the implementation of desirable control for the core can improve security and effectiveness of the nuclear power plant. Generally speaking, the reactor core control contains the power (or coolant temperature) control and axial power difference (namely power distribution) control of the core. The core power control is to regulate the core power, and the core load following control is to regulate the core power and axial power difference simultaneously. Modeling reactor cores is the inevitable preliminary work for research of reactor core control. Over the decades, continuous work has been devoted to the research of including modeling, power and load following control for reactor cores. In this paper, the review on advanced technologies for modeling, power and load following control of reactor cores is presented. Modeling approaches for reactor cores are reviewed such as the point reactor core modeling. Power control methods for reactor cores are reviewed such as the feedback control with a state observer. Load following control techniques for reactor cores are reviewed such as Mode A, Mode G, Mode T, Mechanical Shim and advanced control methods of containing multivariable frequency control, etc. The review in this paper can contribute to comprehend the past work with respective advantages, and then exploit novel research directions for development of nuclear power plants. Crown Copyright (C) 2016 Published by Elsevier Ltd. All rights reserved.
机译:这项调查旨在审查用于发电的核电厂反应堆堆芯建模和控制的先进技术。核电站反应堆堆芯是放射性核燃料的热源,是关键部分,具有安全隐患和经济潜力。核电厂无法执行其核的所需控制可能导致更高的运营成本或系统安全性和可靠性降低,并且对核实施所需的控制可以提高核电厂的安全性和有效性。一般而言,反应堆堆芯控制包含堆芯的功率(或冷却液温度)控制和轴向功率差(即功率分配)控制。核心功率控制是调节核心功率,而核心负载跟随控制是同时调节核心功率和轴向功率差。对堆芯进行建模是研究堆芯控制的必然的初步工作。几十年来,持续不断的研究致力于包括对反应堆堆芯的建模,功率和负荷跟踪控制在内的研究。在本文中,将介绍对堆芯控制进行建模,功率和负荷跟踪的先进技术的综述。审查了反应堆堆芯的建模方法,例如点反应堆堆芯建模。审查了用于反应堆堆芯的功率控制方法,例如使用状态观察器进行反馈控制。综述了电抗器堆芯的负荷跟随控制技术,如模式A,模式G,模式T,机械垫片以及包含多变量频率控制的高级控制方法等。本文的综述可有助于理解过去的工作,并具有各自的优势,然后为核电站的开发探索新的研究方向。 Crown版权所有(C)2016,由Elsevier Ltd.发行。保留所有权利。

著录项

  • 来源
    《Renewable & Sustainable Energy Reviews》 |2016年第7期|116-128|共13页
  • 作者单位

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China|Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China;

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China|Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China;

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China|Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China;

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China|Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China;

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Harbin Inst Technol, Sch Astronaut, Harbin 150001, Peoples R China;

    Tsinghua Natl Lab Informat Sci & Technol, Beijing 100084, Peoples R China|Tsinghua Univ, Grad Sch Shenzhen, Shenzhen 518055, Peoples R China|Tsinghua Univ, Dept Automat, Beijing 100084, Peoples R China;

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

    Nuclear power plant; Reactor core; Electricity generation; Modeling; Power control; Load following control;

    机译:核电站;反应堆堆芯;发电;建模;功率控制;负荷跟踪控制;

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