• English
  • العربية
  • 中文
  • Français
  • Русский
  • Español

Conventional Pressurized Water Reactor (PHWR) Simulator

The conventional PHWR simulator was originally developed to assist Atomic Energy of Canada Limited (AECL) in the design of the plant display system. It was developed by CTI Simulation International Corporation in 2005. The conventional PHWR simulator operational specifics are listed as follows:

  • The simulator operates essentially in real time, and has a dynamic response with sufficient fidelity to provide realistic signals to the plant display system.
  • It has a user–machine interface that mimics the actual control panel instrumentation, including the plant display system, to a degree that permits operation of the simulator in a standalone mode, i.e. in the absence of the plant display system equipment. These features also made the simulator suitable as an educational and training tool.
  • The plant model is CANDU, the Canadian designed PHWR with electrical output of 900 MWe.
  • There are a number of PHWR plants in the world that belong to this category, such as: Darlington in Canada, Cernavoda in Romania, Qinshan3 in China. More information about these reactors can be found in the IAEA PRIS data base.
  • The emphasis in developing the simulation models was on giving the desired level of realism to the user in displaying those plant parameters that are most critical to the plant, including the ones that characterize the main processes, control and protective systems.
  • The interaction between the user and the simulator is via a combination of monitor displays, mouse and keyboard. Parameter monitoring and operator controls implemented via the plant display system at the generating station are represented in a virtually identical manner. Control panel instruments and control devices, such as push–buttons and hand–switches, are shown as stylized pictures, and are operated via special pop–up menus and dialog boxes in response to user inputs.
  • There is no possibility to model severe accidents.

Normal Operation

  • Power Reduction/Increase
  • Normal Reactor Trip

Malfunction Transient Events

  • Reactor Setback and Stepback Fail
  • One Bank of Control Rods Drop into the Reactor
  • Main Circuit Relief Valve Fails Open
  • Pressurizer Relief Valve Fails Open
  • Pressurizer Isolation Valve Fails Closed
  • Feed Valve Fails Open
  • Bleed Valve Fails Open
  • Reactor Header Break
  • All Level Control Isolation Valves Fail Closed
  • One Level Control Valve Fails Open/Closed
  • All Feedwater Pumps Trip
  • All Safety Valves Open
  • Steam Header Break


  1. Employment
  2. Women
  3. Press

Stay in touch