Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Standard

Development of new cladding types for nuclear fuel : IOP Conference Series: Materials Science and Engineering. / Hózer, Zoltán; Novotny, T.; Perez-Feró, E.; Horváth, M. ; Szabó, P.; Illés, L.; Schyns, Marc; Delville, Rémi; Kim, D.; Sevecek, M.

IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary. Vol. 903 2020. p. 1-9 012004 (IOP Conference Series: Materials Science and Engineering; Vol. 903).

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Hózer, Z, Novotny, T, Perez-Feró, E, Horváth, M, Szabó, P, Illés, L, Schyns, M, Delville, R, Kim, D & Sevecek, M 2020, Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering. in IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary. vol. 903, 012004, IOP Conference Series: Materials Science and Engineering, vol. 903, pp. 1-9. https://doi.org/10.1088/1757-899X/903/1/012004

APA

Hózer, Z., Novotny, T., Perez-Feró, E., Horváth, M., Szabó, P., Illés, L., ... Sevecek, M. (2020). Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering. In IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary (Vol. 903, pp. 1-9). [012004] (IOP Conference Series: Materials Science and Engineering; Vol. 903). https://doi.org/10.1088/1757-899X/903/1/012004

Vancouver

Hózer Z, Novotny T, Perez-Feró E, Horváth M, Szabó P, Illés L et al. Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering. In IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary. Vol. 903. 2020. p. 1-9. 012004. (IOP Conference Series: Materials Science and Engineering). https://doi.org/10.1088/1757-899X/903/1/012004

Author

Hózer, Zoltán ; Novotny, T. ; Perez-Feró, E. ; Horváth, M. ; Szabó, P. ; Illés, L. ; Schyns, Marc ; Delville, Rémi ; Kim, D. ; Sevecek, M. / Development of new cladding types for nuclear fuel : IOP Conference Series: Materials Science and Engineering. IOP Conference Series: Materials Science and Engineering: 12th Hungarian Conference on Materials Science (HMSC12) 13-15 October 2019, Balatonkenese, Hungary. Vol. 903 2020. pp. 1-9 (IOP Conference Series: Materials Science and Engineering).

Bibtex - Download

@inproceedings{4295140fd95541a88441058ab48a5c4d,
title = "Development of new cladding types for nuclear fuel: IOP Conference Series: Materials Science and Engineering",
abstract = "Three different cladding types were tested for nuclear fuel in traditional light water reactors and generation IV gas-cooled fast reactors. Cr coated Zr cladding was tested in steam atmosphere up to 1200 °C to demonstrate moderate oxidation and hydrogen production in accident conditions. 15-15Ti stainless steel alloy and SiCf/SiC cladding tube samples were treated in helium atmosphere with different impurities for several hours at 1000 °C. Additional mechanical testing and microstructure examinations were carried out with as-received samples and with specimens after high temperature treatments. The experiments results indicated the applicability of the tested materials for reactor conditions in the investigated range of parameters.",
keywords = "Cladding, Coating, Chromium, Oxidation",
author = "Zolt{\'a}n H{\'o}zer and T. Novotny and E. Perez-Fer{\'o} and M. Horv{\'a}th and P. Szab{\'o} and L. Ill{\'e}s and Marc Schyns and R{\'e}mi Delville and D. Kim and M. Sevecek",
note = "Score=3",
year = "2020",
month = "12",
day = "4",
doi = "10.1088/1757-899X/903/1/012004",
language = "English",
volume = "903",
series = "IOP Conference Series: Materials Science and Engineering",
publisher = "IOP Publishing Ltd",
pages = "1--9",
booktitle = "IOP Conference Series: Materials Science and Engineering",

}

RIS - Download

TY - GEN

T1 - Development of new cladding types for nuclear fuel

T2 - IOP Conference Series: Materials Science and Engineering

AU - Hózer, Zoltán

AU - Novotny, T.

AU - Perez-Feró, E.

AU - Horváth, M.

AU - Szabó, P.

AU - Illés, L.

AU - Schyns, Marc

AU - Delville, Rémi

AU - Kim, D.

AU - Sevecek, M.

N1 - Score=3

PY - 2020/12/4

Y1 - 2020/12/4

N2 - Three different cladding types were tested for nuclear fuel in traditional light water reactors and generation IV gas-cooled fast reactors. Cr coated Zr cladding was tested in steam atmosphere up to 1200 °C to demonstrate moderate oxidation and hydrogen production in accident conditions. 15-15Ti stainless steel alloy and SiCf/SiC cladding tube samples were treated in helium atmosphere with different impurities for several hours at 1000 °C. Additional mechanical testing and microstructure examinations were carried out with as-received samples and with specimens after high temperature treatments. The experiments results indicated the applicability of the tested materials for reactor conditions in the investigated range of parameters.

AB - Three different cladding types were tested for nuclear fuel in traditional light water reactors and generation IV gas-cooled fast reactors. Cr coated Zr cladding was tested in steam atmosphere up to 1200 °C to demonstrate moderate oxidation and hydrogen production in accident conditions. 15-15Ti stainless steel alloy and SiCf/SiC cladding tube samples were treated in helium atmosphere with different impurities for several hours at 1000 °C. Additional mechanical testing and microstructure examinations were carried out with as-received samples and with specimens after high temperature treatments. The experiments results indicated the applicability of the tested materials for reactor conditions in the investigated range of parameters.

KW - Cladding

KW - Coating

KW - Chromium

KW - Oxidation

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/41677033

U2 - 10.1088/1757-899X/903/1/012004

DO - 10.1088/1757-899X/903/1/012004

M3 - In-proceedings paper

VL - 903

T3 - IOP Conference Series: Materials Science and Engineering

SP - 1

EP - 9

BT - IOP Conference Series: Materials Science and Engineering

ER -

ID: 6987834