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Preliminary validation of ASTEC V2.2.b with the QUENCH-20 BWR bundle experiment

Murat, Onur; Sanchez-Espinoza, Victor; Wang, Shisheng; Stuckert, Juri

Abstract (englisch):
ASTEC is an integral severe accident code which aims to simulate entire severe accident transients of the nuclear reactors. New BWR-related models are implemented in the new versions of European ASTEC integral code by IRSN for BWR-typical core structures such as absorber blades, canister, etc. during the In-vessel core degradation after a severe accident in a BWR. The goal is to improve the simulation of the whole severe accident sequence in a BWR, such as the Fukushima accidents. An important step is the validation of the new models (oxidation, molten material formation and melt relocation, etc.) before the code is used to simulate severe accident scenarios in BWRs. The QUENCH-20 BWR test was specifically performed to investigate the oxidation, hydrogen generation, melt formation and oxidation during the reflooding of the test section representing a quarter of a SVEA-96 Optima-2 fuel assembly. The data measured during the QUENCH-20 BWR test e.g. temperature of the fuel rod simulators, of the blade and of the canister as well as the hydrogen production, quench front movement is used for the validation of the code’s prediction capability. ... mehr



Originalveröffentlichung
DOI: 10.1016/j.nucengdes.2020.110931
Zugehörige Institution(en) am KIT Institut für Angewandte Materialien - Angewandte Werkstoffphysik (IAM-AWP)
Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 12.2020
Sprache Englisch
Identifikator ISSN: 0029-5493
KITopen-ID: 1000125834
HGF-Programm 32.12.02 (POF IV, LK 01)
Beyond Design Basis and Emergency Management
Erschienen in Nuclear engineering and design
Band 370
Seiten 110931
Schlagwörter ASTEC, QUENCH, Severe accident, BWR, Reflooding
Nachgewiesen in Scopus
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