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IAEA FUMAC Benchmark on the Halden, Studisvik and QUENCH-L1 LOCA tests

Pizzocri, D.; Bouloré, A.; Stuckert, J. ORCID iD icon; Van Uffelen, P.; Wiesenack, W.; Zhang, J.

Abstract (englisch):

The International Atomic Energy Agency (IAEA) sponsored the Coordinated Research Project (CRP) on Fuel Modeling under Accident Conditions (FUMAC) to coordinate and support research on nuclear fuel modelling under accident conditions in member countries. The focus of the FUMAC CRP (2015-2018) has been on loss-of-coolant accidents (LOCA). Various institutions performed fuel performance simulations of selected experiments using different fuel performance codes (e.g., FRAPCON-FRAPTRAN, TRANSURANUS, ALCYONE, DIONISIO, SOCRAT, FTPAC, BISON, RAPTA) and system codes (e.g SOCRATE, ATHLET). One of the results of the FUMAC CRP is a comprehensive code-to-code benchmark of selected results, and a comparison of simulations with experimental data as well. This paper represents an overview of the current state-of-the-art of nuclear fuel simulation capabilities for LOCAs and paves the way to further analyses and future developments. More precisely, we discuss the results of the simulation of a subset of the experiments considered in the FUMAC CRP, i.e., (i) the Halden LOCA tests (IFA-650.9/10/11, but only IFA-650.10 is in detail presented in this paper), (ii) the Studsvik LOCA test NRC-192, and (iii) rod 4 of the KIT QUENCH-L1 bundle test. ... mehr

Zugehörige Institution(en) am KIT Institut für Angewandte Materialien – Angewandte Werkstoffphysik (IAM-AWP)
Publikationstyp Proceedingsbeitrag
Publikationsjahr 2018
Sprache Englisch
Identifikator KITopen-ID: 1000093945
HGF-Programm 32.02.11 (POF III, LK 01) Auslegungsüberschreitende Störfälle
Erschienen in TOPFUEL Reactor Fuel Performance, Prag, Czech Republic, 30 September - 04 October 2018
Veranstaltung TOPFUEL Reactor Fuel Performance (2018), Prag, Tschechien, 30.09.2018 – 04.10.2018
Seiten Paper A0222
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