Tereshnok, V.A., Stepanov, V.P., Zhukov, A.G., Salnikov, A.A. and Lebedev, O. (2009) The Studies of Operating Conditions Involving a Loss of a Single Reactor Coolant Pump out of Four Running Reactor Coolant Pumps with Fast Power Reduction System Actuation during Rostov Unit 1 Operation at Slightly Increased Reactor Rated Power. The 6th International Conference on Safety Assurance of NPPs with WWER, OKB.GidroPress, Podolsk, 26-29 May 2009. (In Russian)

has been cited by the following article:

• TITLE: Verification of VVER-1200 NPP Simulator in Normal Operation and Reactor Coolant Pump Coast-Down Transient

  AUTHORS: Le Dai Dien, Do Ngoc Diep

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

  JOURNAL NAME: World Journal of Engineering and Technology, Vol.5 No.3, August 21, 2017

  ABSTRACT: 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.