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Model-free adaptive control law for nuclear superheated-steam supply systems

机译:核过热蒸汽供应系统的无模型自适应控制律

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摘要

Nuclear steam supply system (NSSS), which provides saturated or superheated steam to the secondary loop system for electricity or cogeneration, is central in a nuclear plant. The control of NSSS is important for the safe, stable and efficient plant operation. Nuclear superheated-steam supply system (Su-NSSS), which is equipped with an under moderated fission reactor and a once-through steam generator (OTSG) for producing superheated steam flow, is an important type of NSSS that widely applied in the nuclear plants based on the common large pressurized water reactors (PWR) and small modular reactors (SMRs) such as integral PWR (iPWR) and modular high temperature gas-cooled reactor (MHTGR). There is still very limited results for the control of Su-NSSS. Motivated by the gap between the importance and the lack of results in the field of Su-NSSS control, a model-free adaptive power-level control law is developed for Su-NSSSs with forced primary circulation in this paper. This new control law is free from physical and thermal-hydraulic parameters, is in the simple proportional-integral (PI) or proportional-differential (PD) form. To verify the feasibility of the newly-built Su-NSSS controller, it is applied to the NSSS control of a two modular high temperature gas-cooled nuclear plant with comparison to a specific MHTGR-based NSSS control law. Numerical simulation results show that this new control law can improve the transient performance of neutron flux and steam temperature in normal operation case, and can realize system resilience in some abnormal cases. (C) 2017 Elsevier Ltd. All rights reserved.
机译:核蒸汽供应系统(NSSS)为核电站的中心提供饱和或过热的蒸汽给次级回路系统以进行发电或热电联产。 NSSS的控制对于安全,稳定和高效的工厂运营至关重要。核过热蒸汽供应系统(Su-NSSS)配备了一个温和裂变反应堆和一个用于产生过热蒸汽流的直流蒸汽发生器(OTSG),是广泛应用在核电站中的重要NSSS类型。基于常见的大型压水堆(PWR)和小型模块化反应堆(SMR),例如整体式PWR(iPWR)和模块化高温气冷堆(MHTGR)。 Su-NSSS的控制结果仍然非常有限。由于Su-NSSS控制领域的重要性与结果缺乏之间的差距,本文针对具有强制一次循环的Su-NSSSs,开发了一种无模型的自适应功率级控制律。这个新的控制定律没有物理和热工液压参数,采用简单的比例积分(PI)或比例微分(PD)形式。为了验证新型Su-NSSS控制器的可行性,与基于MHTGR的特定NSSS控制律相比,将其应用于两个模块化高温气冷核电站的NSSS控制。数值仿真结果表明,该新的控制规律在正常运行情况下可以改善中子通量和蒸汽温度的暂态性能,在某些异常情况下可以实现系统的弹性。 (C)2017 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Energy》 |2017年第15期|53-67|共15页
  • 作者单位

    Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol INET,Collaborat In, Beijing 100084, Peoples R China;

    Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol INET,Collaborat In, Beijing 100084, Peoples R China;

    Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol INET,Collaborat In, Beijing 100084, Peoples R China;

    Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol INET,Collaborat In, Beijing 100084, Peoples R China;

    Tsinghua Univ, Minist Educ, Key Lab Adv Reactor Engn & Safety, Inst Nucl & New Energy Technol INET,Collaborat In, Beijing 100084, Peoples R China;

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

    Nuclear fission energy; Nuclear steam supply system; Superheated steam; Control; Model free; Adaptation;

    机译:核裂变能;核蒸汽供应系统;过热蒸汽;控制;无模型;适应;

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