Conveners
6.1 CFD and 3D Modeling
- Leonid Bolshov (Nuclear Safety Institute of the Russian Academy of Sciences)
- Velusamy Karuppanna Gounder (Indira Gandhi Centre for Atomic Research)
Dr
Dmitry Fomichev
(JSC NIKIET)
6/26/17, 1:00 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
This paper presents an analysis of hydraulic and heat transfer phenomena in a lead coolant flow in a fuel assembly (FA) of the BREST-OD-300 reactor core central subzone based on CFD simulations (RANS) using the STAR-CCM+ code. Based on the simulation results, coolant pressure, velocity and temperature fields, and the fuel cladding temperature distribution have been obtained. The FA design...
Dr
Velusamy Karuppanna Gounder
(Indira Gandhi Centre for Atomic Research)
6/26/17, 1:20 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
One dimensional steady state model is developed for counter current shell and tube once through steam generator for PFBR with water flowing through tubes and sodium through shell. All the heat transfer processes i.e. preheating, evaporation of water and superheating of the steam happen along the length of the tube. The length of the steam generator is divided into a number of control volumes....
Mrs
Vladimir Chudanov
(Nuclear Safety Insitute RAS (IBRAE))
6/26/17, 1:40 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
For the simulation of the thermalhydraulic processes in fast reactors with liquid metal coolant DNS CFD code CONV-3D has been developed.
This code has ideal scalability and is very effective for calculations on high performance cluster computers.
The code has been validated on the set of analytical tests and experiments in a wide range of Rayleigh and Reynolds numbers, in particular, at...
Mr
Venkatesan Arasappan
(Indira Gandhi Centre for Atomic Research)
6/26/17, 2:00 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Recent advances in computer science have paved way to increased ease in design of nuclear power plants and imparting efficient operator training thereby improving the safety of nuclear plants. As nuclear power plant is considered safety critical, need to improve the skill set of the control room operators by getting the operator trained in simulator is becoming a mandatory requirement before...
Hiroyuki Ohshima
(Japan Atomic Energy Agency)
6/26/17, 2:20 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
A numerical simulation system, which consists of a deformation analysis program and three kinds of thermal-hydraulic analysis programs, is being developed in Japan Atomic Energy Agency in order to offer methodologies to clarify thermal-hydraulic phenomena in fuel assemblies of sodium-cooled fast reactors under various operating conditions including fuel deformation. In this paper, we focus on...
Prof.
Zhao-Fei TIAN
(Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University)
6/26/17, 2:40 PM
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In this paper, the graphics interface and parameter modeling real-time simulation software, Jtopmeret, was used to model and simulate the intermediate heat transport system and the steam power conversion system of China Experimental Fast Reactor (CEFR). The two-phase, multi-component models were taken into consideration to simulate the flow and heat transfer of working medium sodium and...
