Published 1976 | Version v1
Book

Dynamic behaviour of CANDU reactor

  • 1. B.H.E.L. Consultancy Services, New Delhi (India)
  • 2. Indian Inst. of Tech., Kanpur. Dept. of Mechanical Engineering and Nuclear Centre
  • 3. Indian Inst. of Tech., Kanpur. Dept. of Electrical Engineering

Description

Understanding of the dynamic behaviour of a reactor system in a power station is essential for evolving control stragies as well as design modifications. The dynamic behaviour of Rajasthan Atomic Power Station is studied. Mathematical models for the reactor, the steam generator and the steam drum with the natural circulation loop are developed from physical principles like conservation of mass, momentum and energy. Each of these models is then simulated on a digital computer to obtain the characteristics during transients. The models are then combined to yield a dynamic mathematical model of the system comprising the reactor, the steam generator and the steam drum and this results in a nonlinear model. Using this model, responses of the system for various disturbances like step change in the area of the steam valve, step change in the temperature of feed water are obtained and are discussed. These models could be used to devise new control laws using optimal control theory or to evaluate the performance of existing control schemes. (author)

Additional details

Publishing Information

Publisher
Department of Atomic Energy.
Imprint Place
Bombay
Imprint Title
Proceedings of the symposium on power plant dynamics and control [held at Bombay during] February 23-24, 1976
Journal Page Range
p. 47-54.

Conference

Title
Symposium on power plant dynamics and control.
Dates
23 - 24 Feb 1976.
Place
Bombay, India.