LOCA evaluation considering critical flow model with uncertainty parameters

Ilsuk Lee, Youngseog Bang, Deogyeon Oh, Yong Chan Kim

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The purpose of the present work is to study the sensitivity of uncertainty parameters of critical flow on analysis of LOCA with MARS-KS (Multi-dimensional Analysis for Reactor Safety) used by KINS as independent regulatory assessment. In this paper, the uncertainty of critical flow model is considered by three parameters, thermal non-equilibrium factor, discharge coefficient and length to diameter ratio and it is determined uncertainty ranges by using large-scale Marviken experimental data. Break flow is strongly dependent on thermal non-equilibrium in the ruptured pipe with small L/D ratio, and appropriate thermal non-equilibrium values are provided in this study by analyzing results between Marviken experimental data and MARS-KS code. Additionally, a correlation for the relation between quality at the throat and L/D ratio was developed using the effect of quality with non-equilibrium on the critical mass flow rate. It also evaluated LBLOCA of APR1400 focused on the effect of three uncertainty parameters that affect PCT and the break flow. Results of plant analysis showed that deviation of PCT was 80.5ºC in the uncertainty range owing to super-heated liquid causing from the thermal non-equilibrium.

Original languageEnglish
Title of host publicationPBNC 2018 - Pacific Basin Nuclear Conference
PublisherAmerican Nuclear Society
Pages34-40
Number of pages7
ISBN (Electronic)9780894487743
Publication statusPublished - 2019 Jan 1
Event2018 Pacific Basin Nuclear Conference, PBNC 2018 - San Francisco, United States
Duration: 2018 Sep 302018 Oct 4

Publication series

NamePBNC 2018 - Pacific Basin Nuclear Conference

Conference

Conference2018 Pacific Basin Nuclear Conference, PBNC 2018
CountryUnited States
CitySan Francisco
Period18/9/3018/10/4

Fingerprint

Loss of coolant accidents
Pipe
Flow rate
Uncertainty
Hot Temperature
Liquids

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Lee, I., Bang, Y., Oh, D., & Kim, Y. C. (2019). LOCA evaluation considering critical flow model with uncertainty parameters. In PBNC 2018 - Pacific Basin Nuclear Conference (pp. 34-40). (PBNC 2018 - Pacific Basin Nuclear Conference). American Nuclear Society.

LOCA evaluation considering critical flow model with uncertainty parameters. / Lee, Ilsuk; Bang, Youngseog; Oh, Deogyeon; Kim, Yong Chan.

PBNC 2018 - Pacific Basin Nuclear Conference. American Nuclear Society, 2019. p. 34-40 (PBNC 2018 - Pacific Basin Nuclear Conference).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Lee, I, Bang, Y, Oh, D & Kim, YC 2019, LOCA evaluation considering critical flow model with uncertainty parameters. in PBNC 2018 - Pacific Basin Nuclear Conference. PBNC 2018 - Pacific Basin Nuclear Conference, American Nuclear Society, pp. 34-40, 2018 Pacific Basin Nuclear Conference, PBNC 2018, San Francisco, United States, 18/9/30.
Lee I, Bang Y, Oh D, Kim YC. LOCA evaluation considering critical flow model with uncertainty parameters. In PBNC 2018 - Pacific Basin Nuclear Conference. American Nuclear Society. 2019. p. 34-40. (PBNC 2018 - Pacific Basin Nuclear Conference).
Lee, Ilsuk ; Bang, Youngseog ; Oh, Deogyeon ; Kim, Yong Chan. / LOCA evaluation considering critical flow model with uncertainty parameters. PBNC 2018 - Pacific Basin Nuclear Conference. American Nuclear Society, 2019. pp. 34-40 (PBNC 2018 - Pacific Basin Nuclear Conference).
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