Author(s)

Le Dai Dien¹, Do Ngoc Diep²

¹Nuclear Training Center, VINATOM, Hanoi, Vietnam.
²Vietnam Atomic Energy Agency, Hanoi, Vietnam.

Verification of operation parameters of VVER-1200 NPP Simulator installed at Nuclear Training Center, VINATOM has been performed. This simulator has been supplied for Vietnam in the framework of IAEA TC Project VIE2010 on Developing Nuclear Power Infrastructure—Phase II hosted by the Vietnam Atomic Energy Agency (VAEA). The comparison of the main parameters in nominal power operation with design data given in safety analysis report of VVER-1200/V392M as well as Ninh Thuan FSSAR is presented. In this study, the reactor coolant coast-down transient is investigated using the VVER-1200 NPP simulator. The simulated results performed in the simulator through switching off one reactor coolant pump in comparisons with experiment results performed in VVER-1000 reactor are given. The similarity between the measured and simulated results shows that the thermal hydraulic characteristics and the control protection systems are modeled in a reasonable way. A good agreement in operating parameters was found between the VVER-1200 NPP simulator and VVER-1200/V392M’s PSAR.

Simulator, Human Machine Interfaces, VVER Type Reactor, Reactor Coolant Pump, Control Rod Bank

Dien, L. and Diep, D. (2017) Verification of VVER-1200 NPP Simulator in Normal Operation and Reactor Coolant Pump Coast-Down Transient. World Journal of Engineering and Technology, 5, 507-519. doi: 10.4236/wjet.2017.53043.