Priyanshu Goyal, I. Thangamani, V. Verma, V.M. Shanware, R. K. Singh
Bhabha Atomic Research Centre, Mumbai, India
In a nuclear reactor, the containment is the last barrier for the release of radioactivity during severe accident conditions. Containment material can be concrete or steel or steel-lined concrete. Steel containments have a high load bearing capacity and a high degree of leak tightness at higher pressures. In case of a severe accident, heat can be removed from the containment by a guide panel, ...
F. Mechighel, B. Pateyron, M. El Ganaoui, S. Dost, and M. Kadja
Laboratory SPCTS UMR CNRS, ENSCI, Limoges University, Limoges, France
Crystal Growth Laboratory, Department of Mechanical Engineering, University of Victoria, British Columbia, Victoria, Canada
Department of Mechanical Engineering, University of Constantine, Constantine, Algeria
A numerical simulation study, using COMSOL Multiphysics®, was carried out to examine the temperature and concentration fields in the dissolution process of silicon into germanium melt. This work utilized a simplified configuration which may be considered to be similar material configuration to that used in the Vertical Bridgman growth methods. The concentration profile for the SiGe sample ...
D. Baldissin and D. Lombardo
Compumat S.r.l., Torino, Italy
A two-dimensional mathematical model for the absorption and desorption of H2 in LaNi4.8Al0.2 was developed and experimentally validated. The model is composed of an energy balance, a mass balance and a momentum balance. These differential equations are numerically solved by means of the finite element method using the software COMSOL Multiphysics®. From a comparison between theoretical ...
M. G. Hemanath, C. Meikandamurthy, G. Padmakumar, C. A. Babu, P. Kalyanasundaram, and G. Vaidyanathan
 Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu, India
In the pool type Fast Breeder Reactors the roof structure is penetrated by a number of pumps and heat exchangers which are cylindrical in shape. Argon gas in reactor is sandwiched between the free surface of sodium and the roof structure and can flow in the annular space between the components and roof structure forming a thermosyphon. These hermosyphons not only transport heat from sodium to ...
S. Agarwal, C. A. Babu, P. Kalyanasundaram, and G. Vaidyanathan
Fast Reactor Technology Group, Indira Gandhi Centre for Atomic Research, Kalpakkam
Intermediate heat exchanger (IHX) in a pool-type liquid metal cooled fast breeder reactor is an important heat exchanging component as it transfer heat from the radioactive primary sodium in the pool to the non-radioactive secondary sodium. The secondary sodium ultimately heats up water in a steam Generator (SG) to produce the steam for power generation. Intermediate heat exchanger is a ...
 Alpha Project Service, Vadodara, Gujarat, India
The interaction of a single particle in straight rectangular channel in laminar flow is modelled explicitly using the set of Navier Stokes equation for the fluid motion and Newton momentum equation for the particle motion in Cartesian coordinate system. The evaluation of integral force acting on the particle along with the behaviour of streamlines as a function of Reynolds number ReP < 120 is ...
A. Cammi, V. Di Marcello, C. Fiorina, and L. Luzzi
Nuclear Engineering Division, Department of Energy, Politecnico di Milano, Milano, Italy
The present work is aimed at evaluating the capabilities of COMSOL Multiphysics® to treat heat transfer in Molten Salt Reactors (MSR). The analyzed situation is represented by the molten salt in turbulent regime flowing through a cylindrical channel surrounded by graphite, with both the fluid and the solid generating power. A suitable validation framework has been set up on the basis of an ad ...
O. Ecin, E. Engelien, M. Malek, R. Viga, B. Hosticka, and A. Grabmaier
Institut of Mikroelektronische Systeme, University Duisburg-Essen, Duisburg, Germany
Institut of Elektronische Bauelemente und Schaltungen, University Duisburg-Essen, Duisburg, Germany
This communication reports on a numeric fluid dynamics simulation on a pipe flow model. The basic background is to determine the velocity of a flowing fluid in a pipe by using the Thermal Time-Of-Flight (TTOF) method on water. The visualization of the temperature and velocity distribution in the pipe model is being carried out in order to enable proper design and optimization of the TTOF sensor. ...
C. Heining and N. Aksel
Applied Mechanics and Fluid Dynamics, University of Bayreuth, Bayreuth, Germany
We study the gravity-driven film flow of a Newtonian liquid down an inclined plane. Many applications such as heat- and mass exchangers and evaporators or film coaters require undulated or rippled bottom topographies. In these cases, the interplay of gravity, surface tension and inertia leads to a response of the interface which furthermore strongly depends on the shape of the bottom topography. ...
CFD Analysis of Loss Of Vacuum Accident for Safety Application in Experimental Fusion Reactor Facility
C. Bellecci, P. Gaudio, I. Lupelli, A. Malizia, M.T. Porfiri, R. Quaranta, and M. Richetta
EURATOM, Faculty of Engineering, University of Rome “Tor Vergata”, Roma, Italy
ENEA Nuclear Fusion Tecnologies, Frascati, Roma, Italy
In an experimental nuclear fusion facility dust is generated both during normal machine operations and by macroscopic erosion of the plasma facing materials due to intense thermal loads. This dust can be mobilized by air ingress in case of LOVA (Loss of Vacuum Accident) threaten safety of workers and public. A small facility, Small Tank for Aerosol Removal and Dust (STARDUST), was set up in order ...