Original title: Accident Tolerant Fuel simulation loaded in advanced nuclear power reactor during severe accident conditions
Authors: Hamřík, Lukáš ; Mičian, Peter
Document type: Papers
Language: eng
Publisher: Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií
Abstract: This paper introduces accident tolerant fuels with respect to their current state of development, while the leading causes are briefly mentioned. The main reasons for the development of other cladding materials are presented. Selected types of accident tolerant fuel cladding materials are described in short and then are used for a simulation in a model of advanced power reactor undergoing a severe accident scenario in the MELCOR code.
Keywords: accident tolerant fuel; MELCOR; nuclear fuel; safety analysis; severe accident
Host item entry: Proceedings I of the 30st Conference STUDENT EEICT 2024: General papers, ISBN 978-80-214-6231-1, ISSN 2788-1334

Institution: Brno University of Technology (web)
Document availability information: Fulltext is available in the Brno University of Technology Digital Library.
Original record: https://hdl.handle.net/11012/249227

Permalink: http://www.nusl.cz/ntk/nusl-622580


The record appears in these collections:
Universities and colleges > Public universities > Brno University of Technology
Conference materials > Papers
 Record created 2024-07-21, last modified 2024-07-21


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