Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors. (May 2017)
- Record Type:
- Journal Article
- Title:
- Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors. (May 2017)
- Main Title:
- Improved numerical algorithm and experimental validation of a system thermal-hydraulic/CFD coupling method for multi-scale transient simulations of pool-type reactors
- Authors:
- Toti, A.
Vierendeels, J.
Belloni, F. - Abstract:
- Highlights: A system thermal-hydraulic/CFD coupling methodology is proposed for high-fidelity transient flow analyses. The method is based on domain decomposition and implicit numerical scheme. A novel interface Quasi-Newton algorithm is implemented to improve stability and convergence rate. Preliminary validation analyses on the TALL-3D experiment. Abstract: The paper describes the development and validation of a coupling methodology between the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT, conceived for high fidelity plant-scale safety analyses of pool-type reactors. The computational tool is developed to assess the impact of three-dimensional phenomena occurring in accidental transients such as loss of flow (LOF) in the research reactor MYRRHA, currently in the design phase at the Belgian Nuclear Research Centre, SCKCEN. A partitioned, implicit domain decomposition coupling algorithm is implemented, in which the coupled domains exchange thermal-hydraulics variables at coupling boundary interfaces. Numerical stability and interface convergence rates are improved by a novel interface Quasi-Newton algorithm, which is compared in this paper with previously tested numerical schemes. The developed computational method has been assessed for validation purposes against the experiment performed at the test facility TALL-3D, operated by the Royal Institute of Technology (KTH) in Sweden. This paper details the results of the simulation of a loss ofHighlights: A system thermal-hydraulic/CFD coupling methodology is proposed for high-fidelity transient flow analyses. The method is based on domain decomposition and implicit numerical scheme. A novel interface Quasi-Newton algorithm is implemented to improve stability and convergence rate. Preliminary validation analyses on the TALL-3D experiment. Abstract: The paper describes the development and validation of a coupling methodology between the best-estimate system thermal-hydraulic code RELAP5-3D and the CFD code FLUENT, conceived for high fidelity plant-scale safety analyses of pool-type reactors. The computational tool is developed to assess the impact of three-dimensional phenomena occurring in accidental transients such as loss of flow (LOF) in the research reactor MYRRHA, currently in the design phase at the Belgian Nuclear Research Centre, SCKCEN. A partitioned, implicit domain decomposition coupling algorithm is implemented, in which the coupled domains exchange thermal-hydraulics variables at coupling boundary interfaces. Numerical stability and interface convergence rates are improved by a novel interface Quasi-Newton algorithm, which is compared in this paper with previously tested numerical schemes. The developed computational method has been assessed for validation purposes against the experiment performed at the test facility TALL-3D, operated by the Royal Institute of Technology (KTH) in Sweden. This paper details the results of the simulation of a loss of forced convection test, showing the capability of the developed methodology to predict transients influenced by local three-dimensional phenomena. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 103(2017:May)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 103(2017:May)
- Issue Display:
- Volume 103 (2017)
- Year:
- 2017
- Volume:
- 103
- Issue Sort Value:
- 2017-0103-0000-0000
- Page Start:
- 36
- Page End:
- 48
- Publication Date:
- 2017-05
- Subjects:
- Multi-scale thermal-hydraulics -- Codes coupling -- Pool-type reactors
Nuclear energy -- Periodicals
Nuclear engineering -- Periodicals
621.4805 - Journal URLs:
- http://www.sciencedirect.com/science/journal/03064549 ↗
http://catalog.hathitrust.org/api/volumes/oclc/2243298.html ↗
http://www.elsevier.com/journals ↗ - DOI:
- 10.1016/j.anucene.2017.01.002 ↗
- Languages:
- English
- ISSNs:
- 0306-4549
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 1043.150000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 9023.xml