Development of a general coupling interface for the fuel performance code TRANSURANUS – Tested with the reactor dynamics code DYN3D
- 1. Technical University München, Department of Nuclear Engineering, Boltzmannstr. 15, D-85748 Garching bei München (Germany)
- 2. Helmholtz-Zentrum Dresden – Rossendorf, Reactor Safety Division, P.O. Box 510119, D-01314 Dresden (Germany)
- 3. E.ON Kernkraft GmbH, Tresckowstr. 5, D-30457 Hannover (Germany)
- 4. European Commission, Joint Research Centre, Institute for Transuranium Elements, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)
Description
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 of safety criteria, at a reasonable computational cost
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2014.10.040Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2014.10.040;
- PII
- S0306-4549(14)00579-9;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 84
- Journal Page Range
- p. 73-85
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47019351
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CLADDING; COMPUTER CODES; COMPUTERIZED SIMULATION; CONTROL ELEMENTS; DESIGN BASIS ACCIDENTS; ENTHALPY; FUEL ELEMENTS; PERFORMANCE; REACTIVITY; REACTOR KINETICS; REACTOR SAFETY; ROD EJECTION ACCIDENTS; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; TIME DEPENDENCE
- Descriptors DEC
- ACCIDENTS; DEPOSITION; FLUID MECHANICS; HYDRAULICS; KINETICS; MECHANICS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; SAFETY; SIMULATION; SURFACE COATING; THERMODYNAMIC PROPERTIES
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.