Investigation of the hydrogen production by the FeCrAl nuclear fuel cladding using MELCOR 2.2

Loading...
Thumbnail Image
Date
2022
ORCID
Advisor
Referee
Mark
Journal Title
Journal ISSN
Volume Title
Publisher
Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií
Altmetrics
Abstract
This paper deals with hydrogen production in nuclear power reactors by cladding of the fuel. The description of accident tolerant fuel, especially FeCrAl cladding material and its oxidation is presented. Model is based on Phebus facility, that was build for better understanding of phenomena occurring during severe accidents in light water reactors. Conventional used zirconium cladding was replaced by FeCrAl alloy and simulated by MELCOR code. This software is plant risk assessment tool for simulating light water reactors and its accidents. Results shows significantly decrease of hydrogen production.
Description
Citation
Proceedings II of the 28st Conference STUDENT EEICT 2022: Selected papers. s. 220-224. ISBN 978-80-214-6030-0
https://conf.feec.vutbr.cz/eeict/index/pages/view/ke_stazeni
Document type
Peer-reviewed
Document version
Published version
Date of access to the full text
Language of document
en
Study field
Comittee
Date of acceptance
Defence
Result of defence
Document licence
© Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií
Citace PRO