Publication detail

Accident Tolerant Fuel simulation loaded in advanced nuclear power reactor during severe accident conditions

HAMŘÍK, L. MIČIAN, P.

Original Title

Accident Tolerant Fuel simulation loaded in advanced nuclear power reactor during severe accident conditions

Type

article in a collection out of WoS and Scopus

Language

English

Original 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

nuclear fuel; accident tolerant fuel; safety analysis; severe accident; MELCOR

Authors

HAMŘÍK, L.; MIČIAN, P.

Released

9. 7. 2024

Publisher

Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií

Location

Brno

ISBN

978-80-214-6231-1

Book

Proceedings I of the 30st Conference STUDENT EEICT 2024: General papers.

Edition

1

ISBN

2788-1334

Periodical

Proceedings II of the Conference STUDENT EEICT

State

Czech Republic

Pages from

174

Pages to

177

Pages count

4

URL

https://dspace.vut.cz/items/a895abcf-33d6-454d-a36a-165df3258c5c/full

BibTex

@inproceedings{BUT189227,
  author="Lukáš {Hamřík} and Peter {Mičian}",
  title="Accident Tolerant Fuel simulation loaded in advanced nuclear power reactor during severe accident conditions",
  booktitle="Proceedings I of the 30st Conference STUDENT EEICT 2024: General papers.",
  year="2024",
  series="1",
  journal="Proceedings II of the Conference STUDENT EEICT",
  pages="174--177",
  publisher="Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií",
  address="Brno",
  isbn="978-80-214-6231-1",
  issn="2788-1334",
  url="https://dspace.vut.cz/items/a895abcf-33d6-454d-a36a-165df3258c5c/full"
}