Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D. (October 2015)
- Record Type:
- Journal Article
- Title:
- Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D. (October 2015)
- Main Title:
- Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D
- Authors:
- Holt, L.
Rohde, U.
Seidl, M.
Schubert, A.
Van Uffelen, P.
Macián-Juan, R. - Abstract:
- Highlights: A general coupling interface was developed for couplings of the TRANSURANUS code. With this new tool simplified fuel behavior models in codes can be replaced. Applicable e.g. for several reactor types and from normal operation up to DBA. The general coupling interface was applied to the reactor dynamics code DYN3D. The new coupled code system DYN3D–TRANSURANUS was successfully tested for RIA. Abstract: A general interface is presented for coupling the TRANSURANUS fuel performance code with thermal hydraulics system, sub-channel thermal hydraulics, computational fluid dynamics (CFD) or reactor dynamics codes. As first application the reactor dynamics code DYN3D was coupled at assembly level in order to describe the fuel behavior in more detail. In the coupling, DYN3D provides process time, time-dependent rod power and thermal hydraulics conditions to TRANSURANUS, which in case of the two-way coupling approach transfers parameters like fuel temperature and cladding temperature back to DYN3D. Results of the coupled code system are presented for the reactivity transient scenario, initiated by control rod ejection. More precisely, the two-way coupling approach systematically calculates higher maximum values for the node fuel enthalpy. These differences can be explained thanks to the greater detail in fuel behavior modeling. The numerical performance for DYN3D–TRANSURANUS was proved to be fast and stable. The coupled code system can therefore improve the assessment ofHighlights: A general coupling interface was developed for couplings of the TRANSURANUS code. With this new tool simplified fuel behavior models in codes can be replaced. Applicable e.g. for several reactor types and from normal operation up to DBA. The general coupling interface was applied to the reactor dynamics code DYN3D. The new coupled code system DYN3D–TRANSURANUS was successfully tested for RIA. Abstract: A general interface is presented for coupling the TRANSURANUS fuel performance code with thermal hydraulics system, sub-channel thermal hydraulics, computational fluid dynamics (CFD) or reactor dynamics codes. As first application the reactor dynamics code DYN3D was coupled at assembly level in order to describe the fuel behavior in more detail. In the coupling, DYN3D provides process time, time-dependent rod power and thermal hydraulics conditions to TRANSURANUS, which in case of the two-way coupling approach transfers parameters like fuel temperature and cladding temperature back to DYN3D. Results of the coupled code system are presented for the reactivity transient scenario, initiated by control rod ejection. More precisely, the two-way coupling approach systematically calculates higher maximum values for the node fuel enthalpy. These differences can be explained thanks to the greater detail in fuel behavior modeling. The numerical performance for DYN3D–TRANSURANUS was proved to be fast and stable. The coupled code system can therefore improve the assessment of safety criteria, at a reasonable computational cost. … (more)
- Is Part Of:
- Annals of nuclear energy. Volume 84(2015:Oct.)
- Journal:
- Annals of nuclear energy
- Issue:
- Volume 84(2015:Oct.)
- Issue Display:
- Volume 84 (2015)
- Year:
- 2015
- Volume:
- 84
- Issue Sort Value:
- 2015-0084-0000-0000
- Page Start:
- 73
- Page End:
- 85
- Publication Date:
- 2015-10
- Subjects:
- General TRANSURANUS coupling interface -- Fuel performance modeling -- Two-way coupling approach -- DYN3D–TRANSURANUS -- RIA -- Reactor safety analysis
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.2014.10.040 ↗
- 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:
- 7243.xml