Projects / Programmes
Simulations of two-phase thermalhydraulic phenomena in nuclear engineering by computational fluid dynamics methods
| Code |
Science |
Field |
Subfield |
| 2.03.00 |
Engineering sciences and technologies |
Energy engineering |
|
| Code |
Science |
Field |
| T140 |
Technological sciences |
Energy research |
two-phase thermalhydraulic phenomena, critical heat flux, direct contact condensation, three-dimensional numerical simulations, advanced nuclear technology
Researchers (4)
| no. |
Code |
Name and surname |
Research area |
Role |
Period |
No. of publicationsNo. of publications |
| 1. |
05570 |
PhD Ivo Kljenak |
Energy engineering |
Researcher |
2007 - 2009 |
466 |
| 2. |
16435 |
PhD Boštjan Končar |
Energy engineering |
Head |
2007 - 2009 |
367 |
| 3. |
02852 |
PhD Borut Mavko |
Energy engineering |
Researcher |
2007 - 2009 |
930 |
| 4. |
12057 |
PhD Iztok Tiselj |
Energy engineering |
Researcher |
2007 - 2009 |
469 |
Organisations (1)
| no. |
Code |
Research organisation |
City |
Registration number |
No. of publicationsNo. of publications |
| 1. |
0106 |
Jožef Stefan Institute |
Ljubljana |
5051606000 |
90,753 |
Abstract
Planned research activities belong to the field of nuclear engineering and thermal-hydraulic safety analyses. Understanding of physical mechanisms of two-phase flow transients is important for investigation of new nuclear reactor concepts and for maintaining and improving the safety level of existing nuclear power plants. The topic of the proposed project concerns two key thermal-hydraulic phenomena, which significantly affect the design, safety level and lifetime of nuclear reactors. These are Critical Heat Flux (CHF) and Direct Contact Condensation (DCC). The CHF phenomenon is important for design and safety analyses of light-water reactors and also for design concepts of heat exchangers in the experimental fusion devices. DCC can be described as one of the basic physical mechanisms, which affects the behaviour of the Pressurized Thermal Shock (PTS)in the primary system of pressurized water reactors.
With increased development of high-performance computers, the three-dimensional Computational Fluid Dynamics – CFD methods are put forward in nuclear engineering. With these methods the single-phase and two-phase flow phenomena in complex 3D geometries may be simulated. The main goal of this project will be development of CFD models and methods for three-dimensional simulation of CHF and DCC phenomena.
Significance for science
The research carried out has contributed to the development of science in the following areas:
- Contribute to the understanding of complex two-phase processes in nuclear technology,
- New three'dimensional models of convective boiling
- Contribute to the understanding of the boiling crisis and modeling of critical heat flux in the PWR
- New knowledge about the process of mass and momentum exchange at condensation of steam in a horozontally stratified flow
- Development and improvement of the surface tracking models
Significance for the country
The results of the project are among the basic research in the field of thermal-hydraulic safety analysis and can indirectly contribute to the safe and reliable operation of nuclear power plant Krsko. In a broader sense, this research project contributes to the sustainable and stable supply of electricity, and protecting the environment and inhabitants.
In particular, studies of critical heat flux are also part of the Slovenian contribution to the project of the 7th EU Framework Program NURISP, which started 1.1.2009. Through the NURISP project, education and the exchange of researchers between Slovenia and most other European countries is enabled.
Most important scientific results
Annual report
2008,
final report,
complete report on dLib.si
Most important socioeconomically and culturally relevant results
Annual report
2008,
final report,
complete report on dLib.si
