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3-D Simulation of Fuel Assembly Blockage in MYRRHA

Chen, Xue-Nong; Rineiski, Andrei

Abstract (englisch):
In the framework of the KIT and SCK•CEN R&D cooperation and as continuation of earlier studies performed for the EURATOM FP7 MAXSIMA project, accidental transients caused by a single fuel assembly (FA) block-age were simulated with the SIMMER-IV (3-D) code for the MYRRHA core, while assuming no power variation during the accident. A 7-FA model that includes mesh cells for inter-wrap-per gaps between FAs was applied, with the blockage of the central FA. Sensitivity analyses on the gap flow rate, fuel chunk jamming fraction, insulator pellet material were performed in order to identify a conservative case that maximises the chance of damage propagation from the blocked FA to the neighbouring ones. All calculations with different options and parameters did show the same sequence in the blocked FA, including melting of pin cladding, fuel pellet failure, small can-wall break-up, steel particle and fuel chunk accumulation leading to additional blockages, and large can-wall break-up. Finally, fuel chunks are swept out from this FA through the inter-wrapper gaps. In the calculations performed for several tens of seconds and longer, no canwall break-up in the neighbouring FAs has been observed. ... mehr

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Verlagsausgabe §
DOI: 10.5445/IR/1000131282
Veröffentlicht am 13.04.2021
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Thermische Energietechnik und Sicherheit (ITES)
Publikationstyp Buchaufsatz
Publikationsjahr 2021
Sprache Deutsch
Identifikator ISBN: 978-3-7315-1049-9
KITopen-ID: 1000131282
HGF-Programm 32.11.02 (POF IV, LK 01) Predisposal
Erschienen in Annual Report 2019 of the Institute for Nuclear and Energy Technologies
Verlag Karlsruher Institut für Technologie (KIT)
Seiten 17-22
Serie KIT Scientific Reports ; 7759
Bemerkung zur Veröffentlichung The paper is based on the presentation by X.N. Chen et al. at TCADS-4, Fourth International Workshop on Technology and Components of Accelerator-Driven Systems, Antwerp, Belgium, 14-17 October 2019.
Schlagwörter Reactor safety study, LBE cooled reactor, MYRRHA, SIMMER code, 3-D simulations, Fuel assembly blockage accident
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