Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps. It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural ci...

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Autores principales:	Ayako ONO, Masaaki TANAKA, Yasuhiro MIYAKE, Erina HAMASE, Toshiki EZURE
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	sodium-cooled fast reactor decay heat removal system dipped-type direct heat exchanger natural circulation thermal-hydraulics in reactor vessel numerical simulation Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/82e37c2ecfc6479795ae3d20a3b898d0
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spelling	oai:doaj.org-article:82e37c2ecfc6479795ae3d20a3b898d02021-11-29T05:56:30ZPreliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition2187-974510.1299/mej.19-00546https://doaj.org/article/82e37c2ecfc6479795ae3d20a3b898d02020-02-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00546/_pdf/-char/enhttps://doaj.org/toc/2187-9745Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps. It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural circulation not only for the normal operating condition but also for severe accident conditions. In this paper, the numerical results of the preliminary analysis for the sodium experimental condition with the PLANDTL-2, in which the core and the upper plenum with a dipped-type direct heat exchanger (DHX) were modeled, are discussed to establish an appropriate numerical models for the reactor core including the gap region among the subassemblies and the DHX. The transient analysis simulating the reactor scram reveals that the 3-dimensional large scale flow structure is developed through the gaps in the whole of the core area during the reactor scram. The steady-state analysis coinciding Richardson number between the PLANDTL-2 and the reactor operation condition reveals that the hot spot and cold spot appear depending on the location of the DHX, which is caused by the complex thermal-hydraulic phenomena driven by the natural circulation. From these preliminary analyses, the characteristics of the thermal-hydraulics behavior in the PLANDTL-2 to be focused are extracted.Ayako ONOMasaaki TANAKAYasuhiro MIYAKEErina HAMASEToshiki EZUREThe Japan Society of Mechanical Engineersarticlesodium-cooled fast reactordecay heat removal systemdipped-type direct heat exchangernatural circulationthermal-hydraulics in reactor vesselnumerical simulationMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00546-19-00546 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	sodium-cooled fast reactor decay heat removal system dipped-type direct heat exchanger natural circulation thermal-hydraulics in reactor vessel numerical simulation Mechanical engineering and machinery TJ1-1570
spellingShingle	sodium-cooled fast reactor decay heat removal system dipped-type direct heat exchanger natural circulation thermal-hydraulics in reactor vessel numerical simulation Mechanical engineering and machinery TJ1-1570 Ayako ONO Masaaki TANAKA Yasuhiro MIYAKE Erina HAMASE Toshiki EZURE Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
description	Fully natural circulation decay heat removal systems (DHRSs) are adopted for sodium fast reactors, which is a passive safety feature without any electrical pumps. It is needed to grasp the thermal-hydraulic phenomena in the reactor vessel and evaluate the coolability of the core under the natural circulation not only for the normal operating condition but also for severe accident conditions. In this paper, the numerical results of the preliminary analysis for the sodium experimental condition with the PLANDTL-2, in which the core and the upper plenum with a dipped-type direct heat exchanger (DHX) were modeled, are discussed to establish an appropriate numerical models for the reactor core including the gap region among the subassemblies and the DHX. The transient analysis simulating the reactor scram reveals that the 3-dimensional large scale flow structure is developed through the gaps in the whole of the core area during the reactor scram. The steady-state analysis coinciding Richardson number between the PLANDTL-2 and the reactor operation condition reveals that the hot spot and cold spot appear depending on the location of the DHX, which is caused by the complex thermal-hydraulic phenomena driven by the natural circulation. From these preliminary analyses, the characteristics of the thermal-hydraulics behavior in the PLANDTL-2 to be focused are extracted.
format	article
author	Ayako ONO Masaaki TANAKA Yasuhiro MIYAKE Erina HAMASE Toshiki EZURE
author_facet	Ayako ONO Masaaki TANAKA Yasuhiro MIYAKE Erina HAMASE Toshiki EZURE
author_sort	Ayako ONO
title	Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
title_short	Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
title_full	Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
title_fullStr	Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
title_full_unstemmed	Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
title_sort	preliminary analysis of sodium experimental apparatus plandtl-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/82e37c2ecfc6479795ae3d20a3b898d0
work_keys_str_mv	AT ayakoono preliminaryanalysisofsodiumexperimentalapparatusplandtl2fordevelopmentofevaluationmethodforthermalhydraulicsinreactorvesselofsodiumfastreactorunderdecayheatremovalsystemoperationcondition AT masaakitanaka preliminaryanalysisofsodiumexperimentalapparatusplandtl2fordevelopmentofevaluationmethodforthermalhydraulicsinreactorvesselofsodiumfastreactorunderdecayheatremovalsystemoperationcondition AT yasuhiromiyake preliminaryanalysisofsodiumexperimentalapparatusplandtl2fordevelopmentofevaluationmethodforthermalhydraulicsinreactorvesselofsodiumfastreactorunderdecayheatremovalsystemoperationcondition AT erinahamase preliminaryanalysisofsodiumexperimentalapparatusplandtl2fordevelopmentofevaluationmethodforthermalhydraulicsinreactorvesselofsodiumfastreactorunderdecayheatremovalsystemoperationcondition AT toshikiezure preliminaryanalysisofsodiumexperimentalapparatusplandtl2fordevelopmentofevaluationmethodforthermalhydraulicsinreactorvesselofsodiumfastreactorunderdecayheatremovalsystemoperationcondition
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Preliminary analysis of sodium experimental apparatus PLANDTL-2 for development of evaluation method for thermal-hydraulics in reactor vessel of sodium fast reactor under decay heat removal system operation condition

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