Detail publikace

VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE

FORAL, Š. KATOVSKÝ, K. SUK, L. POLÁŠEK, R.

Originální název

VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE

Typ

článek ve sborníku ve WoS nebo Scopus

Jazyk

angličtina

Originální abstrakt

One of the tools for safety analysis of light water reactors is the subchannel methodology which is used for evaluation of the limits with regards to departure from nucleate boiling (DNB). This approach utilities subchannel code which has to be validated against experimental data. In this work, the ALTHAMC12 subchannel code is validated against critical heat flux data measured at test section with hexagonal geometry. Validation is performed using the PG-S and OKB correlations of critical heat flux (CHF). The experimental data library is based on public literature sources. The analysis shows that PG-S correlation provides prediction of CHF close to experimental values. The OKB correlation underestimates the CHF and thus provides conservative results for safety analysis.

Klíčová slova

Subchanel code; nuclear thermal hydraulics; DNBR

Autoři

FORAL, Š.; KATOVSKÝ, K.; SUK, L.; POLÁŠEK, R.

Vydáno

11. 11. 2021

Nakladatel

American Nuclear Society

Místo

555 North Kensington Avenue La Grange Park, Illinois 60526 U.S.A.

ISBN

9780894487774

Kniha

ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics

Edice

Proceedings of ANS

Číslo edice

1

Strany od

768

Strany do

781

Strany počet

13

URL

BibTex

@inproceedings{BUT175919,
  author="Štěpán {Foral} and Karel {Katovský} and Ladislav {Suk} and Radek {Polášek}",
  title="VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE",
  booktitle="ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics",
  year="2021",
  series="Proceedings of ANS",
  number="1",
  pages="768--781",
  publisher="American Nuclear Society",
  address="555 North Kensington Avenue
La Grange Park, Illinois 60526
U.S.A.",
  isbn="9780894487774",
  url="https://www.ans.org/pubs/proceedings/article-49145/"
}