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Projects / Programmes source: ARIS

Modelling of nonhomogeneous atmosphere in nuclear power plant containment

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Research activity

Code Science Field Subfield
2.03.00  Engineering sciences and technologies  Energy engineering   

Code Science Field
T160  Technological sciences  Nuclear engineering and technology 
Keywords
nuclear power plant,severe accident,atmosphere,stratification,mixing,hydrogen
Evaluation (rules)
source: COBISS
Evaluation of bibliographic research performance indicators according to ARIS methodology
Citations Citations for bibliographic records in COBIB.SI that are linked to records in citation databases
source: WoS source: Scopus source: COBISS
Researchers (9)
no. Code Name and surname Research area Role Period No. of publications
1.  24256  PhD Miroslav Babić  Process engineering  Junior researcher  2004 - 2007  43 
2.  04143  MSc Ljubo Fabjan  Energy engineering  Technical associate  2004 - 2007  177 
3.  05570  PhD Ivo Kljenak  Energy engineering  Head  2004 - 2007  466 
4.  24075  Tanja Klopčič    Technical associate  2004 - 2007  6 
5.  02852  PhD Borut Mavko  Energy engineering  Researcher  2004 - 2007  930 
6.  06631  PhD Iztok Parzer  Energy engineering  Researcher  2004 - 2006  194 
7.  21181  Zoran Petrič  Energy engineering  Researcher  2005 - 2007  15 
8.  19725  Andrej Sušnik    Technical associate  2004 - 2007  0 
9.  12057  PhD Iztok Tiselj  Energy engineering  Researcher  2004 - 2007  469 
Organisations (1)
no. Code Research organisation City Registration number No. of publications
1.  0106  Jožef Stefan Institute  Ljubljana  5051606000  90,753 
Abstract
The understanding and prediction of hydrogen behaviour in the containment of a nuclear power plant at severe accident conditions is necessary for the planning of mitigation measures to prevent containment failure, which would lead to fission products release to the environment. The subject of the proposed research is modelling of non-homogeneous (in the sense of temperature and species concentration) multi-component atmosphere (air, steam and hydrogen) in nuclear power plant containment at severe accident conditions. The purpose of the research is the prediction of flow and thermal conditions in the containment. Two complementary approaches will be used: a description on local length scale, and a description with lumped-parameter codes. In the description on local scale, the following basic phenomena, which strongly influence atmosphere mixing and stratification, will be particularly considered: gas turbulent flow, gas buoyant flow, and steam condensation on vessel walls and other structures. Transport equations of mass, momentum and energy will be solved using a Computational Fluid Dynamics code. A two-dimensional and a three-dimensional model will be developed. The models will be assessed by comparing calculated results with experimental data from the TOSQAN, MISTRA and THAI facilities. The results of modelling on local scale will serve as a basis for modelling with lumped-parameter codes. An adequate subdivision of larger volumes into smaller cells will be determined and adequate values of flow resistance coefficients for gas flow between cells will be prescribed. In this way, guidelines will be proposed for simulating the non-homogeneous atmosphere in containments of real nuclear power plants using lumped-parameter codes.
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