This article analyzes some of the heat changes occur in reactor when there are changes of the heatflux. This is an issue directly related to the workof predictingincidents and give ways to fix the problem when the plant is in conditions such as startup, normal and abnormaloperations. | VNU Journal of Science: Mathematics – Physics, Vol. 33, No. 3 (2017) 89-94 Analysis of Heat Transfer in the VVER-1200 Reactor’s Heat Channel Dinh Van Thin1,*, Bui Van Loat2, Bui Thi Hong2 1 Department of Nuclear Power, Electric Power University Department of Nuclear Physics, VNU University of Science, 334 Nguyen Trai, Hanoi, Vietnam 2 Received 08 June 2017 Revised 15 August 2017; Accepted 15 September 2017 Abstract: In early 2015, the Government of Vietname has decided to choose VVER-1200 Russian-made technology for building at the Nuclear Power Plant in Ninh Thuan 1, this is the advanced reactor generation III + and the only one has been completed for the first time in the world in August 2016. Vietnam is facing a major challenge, which is how to ensure the acquired technology transfer process, then the safe operation of thisunit. This article analyzes some of the heat changes occur in reactor when there are changes of the heatflux. This is an issue directly related to the workof predictingincidents and give ways to fix the problem when the plant is in conditions such as startup, normal and abnormaloperations. For analysis, the authors used CFD methods, this is a very modern method and have high reliability. The results received have fit well when compared with the safety analysis report of Rosatom published. Keywords: Reactor thermalhydraulics, VVER-1200, CFD. 1. Introduction The core of VVER-1200 reactor is designed with due consideration of the TOR for the reactor plant of NPP-2006, which stipulates considerable increase of the parameters determining the performance of an nuclear power plant– performance factor and availability factor of the Unit as compared to the commercial VVER-1000 reactor. In particular, it is necessary to increase the thermal power to 3200 MW, to provide for 12 months long operation between refuelling taking into account planned outage for refuelling. The basic fuel cycle is considered to have the cycle length about 340 EFFD, .
