Numerical simulation of two-phase flow in 4x4 simulated bundle

An evaluation methodology of a thermal-hydraulics based on a mechanism in light water reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation and unanticipated transient such as under a severe accident. Currently, the evaluation of safety for the nuclear reactor has...

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Autores principales:	Ayako ONO, Susumu YAMASHITA, Takayuki SUZUKI, Hiroyuki YOSHIDA
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	two-phase flow light water reactor fuel bundle vof surface tracking method Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/d6dc8152f79e49ffa9ea2d9ee98b89e8
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spelling	oai:doaj.org-article:d6dc8152f79e49ffa9ea2d9ee98b89e82021-11-29T05:56:31ZNumerical simulation of two-phase flow in 4x4 simulated bundle2187-974510.1299/mej.19-00583https://doaj.org/article/d6dc8152f79e49ffa9ea2d9ee98b89e82020-03-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00583/_pdf/-char/enhttps://doaj.org/toc/2187-9745An evaluation methodology of a thermal-hydraulics based on a mechanism in light water reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation and unanticipated transient such as under a severe accident. Currently, the evaluation of safety for the nuclear reactor has been implemented by a best estimate (BE) code and subchannel analysis code. These analysis codes contain models and empirical correlations. Therefore, the full-scale mock-up tests are needed to evaluate the reliability and validation of code. And the model and empirical correlation are allowed to be applied only in the range where the experiments were implemented. The large mock-up tests are once again needed in order to consider the new geometry and boundary conditions when the design of components is changed. Hence, the 3D detailed numerical simulation by the mechanistically based method is expected to be applied for the preliminary analysis to improve the design of fuel assemblies and evaluate the safety. This 3D detailed numerical simulation can reduce the large mock-up tests. The detailed numerical simulation method can provide much information relating to the two-phase flow such as the bubble size, its velocity, and detailed void distribution which, for example, are needed to predict the critical heat flux based on the mechanism. Moreover, JAEA is implementing the development of the nuclear-thermal-coupling code by using a detailed two-phase flow analysis code based on the VOF method like a JUPITER code. In this study, the numerical simulation of two-phase flow in the 4x4 bundle was examined by numerical simulation code JUPITER in order to examine the possibility of the JUPITER code for the large scale two-phase flow analysis. The simulation results are verified by the previous experimental data of two-phase flow.Ayako ONOSusumu YAMASHITATakayuki SUZUKIHiroyuki YOSHIDAThe Japan Society of Mechanical Engineersarticletwo-phase flowlight water reactorfuel bundlevofsurface tracking methodMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00583-19-00583 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	two-phase flow light water reactor fuel bundle vof surface tracking method Mechanical engineering and machinery TJ1-1570
spellingShingle	two-phase flow light water reactor fuel bundle vof surface tracking method Mechanical engineering and machinery TJ1-1570 Ayako ONO Susumu YAMASHITA Takayuki SUZUKI Hiroyuki YOSHIDA Numerical simulation of two-phase flow in 4x4 simulated bundle
description	An evaluation methodology of a thermal-hydraulics based on a mechanism in light water reactors (LWRs) is needed from a viewpoint of the safety analysis during normal operation and unanticipated transient such as under a severe accident. Currently, the evaluation of safety for the nuclear reactor has been implemented by a best estimate (BE) code and subchannel analysis code. These analysis codes contain models and empirical correlations. Therefore, the full-scale mock-up tests are needed to evaluate the reliability and validation of code. And the model and empirical correlation are allowed to be applied only in the range where the experiments were implemented. The large mock-up tests are once again needed in order to consider the new geometry and boundary conditions when the design of components is changed. Hence, the 3D detailed numerical simulation by the mechanistically based method is expected to be applied for the preliminary analysis to improve the design of fuel assemblies and evaluate the safety. This 3D detailed numerical simulation can reduce the large mock-up tests. The detailed numerical simulation method can provide much information relating to the two-phase flow such as the bubble size, its velocity, and detailed void distribution which, for example, are needed to predict the critical heat flux based on the mechanism. Moreover, JAEA is implementing the development of the nuclear-thermal-coupling code by using a detailed two-phase flow analysis code based on the VOF method like a JUPITER code. In this study, the numerical simulation of two-phase flow in the 4x4 bundle was examined by numerical simulation code JUPITER in order to examine the possibility of the JUPITER code for the large scale two-phase flow analysis. The simulation results are verified by the previous experimental data of two-phase flow.
format	article
author	Ayako ONO Susumu YAMASHITA Takayuki SUZUKI Hiroyuki YOSHIDA
author_facet	Ayako ONO Susumu YAMASHITA Takayuki SUZUKI Hiroyuki YOSHIDA
author_sort	Ayako ONO
title	Numerical simulation of two-phase flow in 4x4 simulated bundle
title_short	Numerical simulation of two-phase flow in 4x4 simulated bundle
title_full	Numerical simulation of two-phase flow in 4x4 simulated bundle
title_fullStr	Numerical simulation of two-phase flow in 4x4 simulated bundle
title_full_unstemmed	Numerical simulation of two-phase flow in 4x4 simulated bundle
title_sort	numerical simulation of two-phase flow in 4x4 simulated bundle
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/d6dc8152f79e49ffa9ea2d9ee98b89e8
work_keys_str_mv	AT ayakoono numericalsimulationoftwophaseflowin4x4simulatedbundle AT susumuyamashita numericalsimulationoftwophaseflowin4x4simulatedbundle AT takayukisuzuki numericalsimulationoftwophaseflowin4x4simulatedbundle AT hiroyukiyoshida numericalsimulationoftwophaseflowin4x4simulatedbundle
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Numerical simulation of two-phase flow in 4x4 simulated bundle

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