Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA

In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5 × 5 test bundle were evaluated for the steady...

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Main Authors: Dae-Hyun Hwang, Seong-Jin Kim, Kyong-Won Seo, Hyuk Kwon
Format: Article
Language:English
Published: Wiley 2012-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2012/603752
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author Dae-Hyun Hwang
Seong-Jin Kim
Kyong-Won Seo
Hyuk Kwon
author_facet Dae-Hyun Hwang
Seong-Jin Kim
Kyong-Won Seo
Hyuk Kwon
author_sort Dae-Hyun Hwang
collection DOAJ
description In the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5 × 5 test bundle were evaluated for the steady-state and transient benchmark data. Optimum values of the turbulent mixing parameter were evaluated for the subchannel exit temperature distribution benchmark. The influence of the mixing vanes on the subchannel flow distribution was investigated through a CFD analysis. In addition, a regionwise turbulent mixing model was examined to account for the nonhomogeneous mixing characteristics caused by the vane effect. The steady-state DNB benchmark data with uniform and nonuniform axial power shapes were evaluated by employing various DNB prediction models: EPRI bundle CHF correlation, AECL-IPPE 1995 CHF lookup table, and representative mechanistic DNB models such as a sublayer dryout model and a bubble crowding model. The DNBR prediction uncertainties for various DNB models were evaluated from a Monte-Carlo simulation for a selected steady-state condition.
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spelling doaj-art-a4ec42c821f644c6ade2e825f67b44b92025-02-03T01:13:13ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832012-01-01201210.1155/2012/603752603752Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRADae-Hyun Hwang0Seong-Jin Kim1Kyong-Won Seo2Hyuk Kwon3Advanced Reactor Development Division, Core Design Department, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of KoreaAdvanced Reactor Development Division, Core Design Department, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of KoreaAdvanced Reactor Development Division, Core Design Department, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of KoreaAdvanced Reactor Development Division, Core Design Department, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353, Republic of KoreaIn the framework of the OECD/NRC PSBT benchmark, the subchannel grade void distribution data and DNB data were assessed by a subchannel code, MATRA. The prediction accuracy and uncertainty of the zone-averaged void fraction at the central region of the 5 × 5 test bundle were evaluated for the steady-state and transient benchmark data. Optimum values of the turbulent mixing parameter were evaluated for the subchannel exit temperature distribution benchmark. The influence of the mixing vanes on the subchannel flow distribution was investigated through a CFD analysis. In addition, a regionwise turbulent mixing model was examined to account for the nonhomogeneous mixing characteristics caused by the vane effect. The steady-state DNB benchmark data with uniform and nonuniform axial power shapes were evaluated by employing various DNB prediction models: EPRI bundle CHF correlation, AECL-IPPE 1995 CHF lookup table, and representative mechanistic DNB models such as a sublayer dryout model and a bubble crowding model. The DNBR prediction uncertainties for various DNB models were evaluated from a Monte-Carlo simulation for a selected steady-state condition.http://dx.doi.org/10.1155/2012/603752
spellingShingle Dae-Hyun Hwang
Seong-Jin Kim
Kyong-Won Seo
Hyuk Kwon
Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
Science and Technology of Nuclear Installations
title Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
title_full Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
title_fullStr Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
title_full_unstemmed Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
title_short Accuracy and Uncertainty Analysis of PSBT Benchmark Exercises Using a Subchannel Code MATRA
title_sort accuracy and uncertainty analysis of psbt benchmark exercises using a subchannel code matra
url http://dx.doi.org/10.1155/2012/603752
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