Extension of the MELCOR code for analysis of late in-vessel phase of a severe accident
2015 (English)In: IYCE 2015 - Proceedings: 2015 5th International Youth Conference on Energy, IEEE conference proceedings, 2015Conference paper (Refereed)Text
The simulation of severe accidents in nuclear power plants with system codes is a powerful tool to improve the safety measures to prevent severe accidents. The further development of severe accident codes is part of current research. MELCOR, as the leading nuclear safety code, provides the possibility to be coupled to other codes. A detailed knowledge of this coupling interface is necessary to use this possibility. Therefore, the software tool DINAMO, which contains the coupling routines and an interface to communicate with other programs, was developed. Using DINAMO it is possible to utilize new models for specific phenomena in MELCOR. In the present work the Phase-Change Effective Convectivity Model was coupled using the CFD-software OpenFOAM and DINAMO to MELCOR to improve the prediction of molten core material in the lower plenum of a reactor pressure vessel. The simulation results were compared to the experimental findings of the LIVE-facility.
Place, publisher, year, edition, pages
IEEE conference proceedings, 2015.
core melt, coupled codes, in-vessel retention, LIVE, MELCOR, nuclear safety, PECM, Accidents, Codes (symbols), Coremaking, Nuclear power plants, Pressure vessels, Safety engineering, Coupled code, Nuclear reactor accidents
Other Engineering and Technologies not elsewhere specified Software Engineering Other Physics Topics
IdentifiersURN: urn:nbn:se:kth:diva-181616DOI: 10.1109/IYCE.2015.7180747ISI: 000381549900019ScopusID: 2-s2.0-84946213927ISBN: 9781467371728OAI: oai:DiVA.org:kth-181616DiVA: diva2:902455
5th International Youth Conference on Energy, IYCE 2015, 27 May 2015 through 30 May 2015
QC 201602112016-02-112016-02-022016-09-23Bibliographically approved