Modelling and Spatial Control of 540 MWe Pressurized Heavy Water Reactor

被引:0
作者
A. P. Tiwari
T. U. Bhatt
Piyush V. Surjagade
机构
[1] Bhabha Atomic Research Centre,Knowledge Management Group
[2] Reactor Control Division of Bhabha Atomic Research Centre,undefined
[3] Homi Bhabha National Institute,undefined
关键词
Nuclear reactor; Spatial control; Modelling; Stability; Transient response; Simulation;
D O I
10.1007/s41403-021-00218-x
中图分类号
学科分类号
摘要
The paper presents the Mathematical Model of 540 MWe Pressurized Heavy Water Reactor (PHWR), which from neutronic viewpoint, is a large reactor. In it, the neutron flux in different parts of the core may experience nonuniform variations with time and to account for such effects, the reactor core is considered to be divided into 14 zones. In each zone, power, delayed neutron precursors’ concentration and xenon and iodine concentrations are represented by their respective volume averaged values in the zone. Neutron diffusion among different zones is modelled through coupling coefficients. This leads to a large number of nonlinear equations characterizing the behaviour of the reactor core. Owing again to the large core size, the reactor is provided with a large number of measuring and reactivity control devices. For complete characterization of the system behaviour, these measuring and control devices have also been modelled. Thus, a very high order model characterized by 132 continuous-time and 75 discrete-time state variables, 14 inputs, 29 direct measurement signals and 15 estimated signals has been obtained for the 540 MWe PHWR. The model has been linearized around steady-state operating point and represented in a standard state space form. The control of the 540 MWe PHWR involves control of both the total power and core power distribution. Each of the fourteen zones of the reactor has been provided with a liquid Zone Control Compartment (ZCC) in which water level can be independently manoeuvred to exercise total power and power distribution control. The water level in each ZCC is also required to be controlled to avoid any instances of flooding or draining. To accomplish these tasks, an output feedback controller has been designed so as to achieve stability and good transient response characteristics. Simulation of typical operational scenarios has been carried out and results thus obtained have been reported.
引用
收藏
页码:731 / 753
页数:22
相关论文
共 50 条
  • [21] Integral Sliding Mode for Power Distribution Control of Advanced Heavy Water Reactor
    Desai, R. J.
    Patre, B. M.
    Munje, R. K.
    Tiwari, A. P.
    Shimjith, S. R.
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2020, 67 (06) : 1076 - 1085
  • [22] Linear active disturbance rejection control for pressurized water reactor power based on partial feedback linearization
    Liu Yuyan
    Liu Jizhen
    Zhou Shiliang
    ANNALS OF NUCLEAR ENERGY, 2020, 137
  • [23] Multi-objective optimization of control parameters for a pressurized water reactor pressurizer using a genetic algorithm
    Wang, Pengfei
    Yan, Xu
    Zhao, Fuyu
    ANNALS OF NUCLEAR ENERGY, 2019, 124 : 9 - 20
  • [24] Design of Fast Output Sampling Controller for Three-Time-Scale Systems: Application to Spatial Control of Advanced Heavy Water Reactor
    Shimjith, Sreyas Rajagopal
    Tiwari, Akhilanand Pati
    Bandyopadhyay, Bijnan
    IEEE TRANSACTIONS ON NUCLEAR SCIENCE, 2011, 58 (06) : 3305 - 3316
  • [25] State-Space Model Predictive Control Method for Core Power Control in Pressurized Water Reactor Nuclear Power Stations
    Wang, Guoxu
    Wu, Jie
    Zeng, Bifan
    Xu, Zhibin
    Wu, Wanqiang
    Ma, Xiaoqian
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2017, 49 (01) : 134 - 140
  • [26] Linear parameter-varying versus linear time-invariant control design for a pressurized water reactor
    Bendotti, P
    Bodenheimer, B
    INTERNATIONAL JOURNAL OF ROBUST AND NONLINEAR CONTROL, 1999, 9 (13) : 969 - 995
  • [27] Optimal design of circulating water system in pressurized water reactor nuclear power plant
    Li, Muping
    Sun, Peiwei
    Wei, Xinyu
    ANNALS OF NUCLEAR ENERGY, 2024, 207
  • [28] Detection of fuel failure in pressurized water reactor with artificial neural network
    Dong, Bing
    Xiao, Wei
    Yin, Junlian
    Wang, Dezhong
    ANNALS OF NUCLEAR ENERGY, 2020, 140
  • [29] Analysis of natural circulation operational characteristics for integrated pressurized water reactor
    Xia, G. L.
    Su, G. H.
    Peng, M. J.
    ANNALS OF NUCLEAR ENERGY, 2016, 92 : 304 - 311