A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan’s specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation IV SFRs. The development of this concept will...

Descripción completa

Guardado en:

Detalles Bibliográficos
Autores principales:	Shigenobu KUBO, Yoshitaka CHIKAZAWA, Hiroyuki OHSHIMA, Masato UCHITA, Takayuki MIYAGAWA, Masao ETO, Tetsuji SUZUNO, Ichiyo MATOBA, Junji ENDO, Osamu WATANABE, Koichi HIGURASHI
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	pool-type sodium-cooled fast reactor anti-seismic design reactor structure three-dimensional thermal hydraulic analysis safety design criteria safety design guidelines Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/123804690f6b4f56881dc87796cf6a72
Etiquetas:	Agregar Etiqueta Sin Etiquetas, Sea el primero en etiquetar este registro!

id	oai:doaj.org-article:123804690f6b4f56881dc87796cf6a72
record_format	dspace
spelling	oai:doaj.org-article:123804690f6b4f56881dc87796cf6a722021-11-29T05:56:30ZA conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability2187-974510.1299/mej.19-00489https://doaj.org/article/123804690f6b4f56881dc87796cf6a722020-03-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00489/_pdf/-char/enhttps://doaj.org/toc/2187-9745The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan’s specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident. The design concepts of a reactor vessel (RV) and its internal structures have been investigated whether they could withstand severe seismic conditions in Japan and thermal loads. The design adopted enhanced RV support structure, enhanced conical-shaped core support structure, a thickened knuckle part of the RV, and a flat plenum separator with ribs. A three-dimensional steady-state thermal hydraulic analysis of the RV revealed that the temperature difference of the upper and lower surfaces of the flat plenum separator could be effectively reduced by installing layers of thermal insulation plates. The authors have also conducted a transient analysis of loss of flow type anticipated transients without scram events to evaluate the feasibility of a self-actuated shutdown system. Moreover, the configuration of the decay heat removal system has been investigated considering sufficient utilization of natural circulation capability of sodium coolant, heat removal capacity of each cooling system, conformance with design requirements, and recommendations of SDC and SDG such as diversity and redundancy of components.Shigenobu KUBOYoshitaka CHIKAZAWAHiroyuki OHSHIMAMasato UCHITATakayuki MIYAGAWAMasao ETOTetsuji SUZUNOIchiyo MATOBAJunji ENDOOsamu WATANABEKoichi HIGURASHIThe Japan Society of Mechanical Engineersarticlepool-type sodium-cooled fast reactoranti-seismic designreactor structurethree-dimensional thermal hydraulic analysissafety design criteriasafety design guidelinesMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00489-19-00489 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	pool-type sodium-cooled fast reactor anti-seismic design reactor structure three-dimensional thermal hydraulic analysis safety design criteria safety design guidelines Mechanical engineering and machinery TJ1-1570
spellingShingle	pool-type sodium-cooled fast reactor anti-seismic design reactor structure three-dimensional thermal hydraulic analysis safety design criteria safety design guidelines Mechanical engineering and machinery TJ1-1570 Shigenobu KUBO Yoshitaka CHIKAZAWA Hiroyuki OHSHIMA Masato UCHITA Takayuki MIYAGAWA Masao ETO Tetsuji SUZUNO Ichiyo MATOBA Junji ENDO Osamu WATANABE Koichi HIGURASHI A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
description	The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan’s specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident. The design concepts of a reactor vessel (RV) and its internal structures have been investigated whether they could withstand severe seismic conditions in Japan and thermal loads. The design adopted enhanced RV support structure, enhanced conical-shaped core support structure, a thickened knuckle part of the RV, and a flat plenum separator with ribs. A three-dimensional steady-state thermal hydraulic analysis of the RV revealed that the temperature difference of the upper and lower surfaces of the flat plenum separator could be effectively reduced by installing layers of thermal insulation plates. The authors have also conducted a transient analysis of loss of flow type anticipated transients without scram events to evaluate the feasibility of a self-actuated shutdown system. Moreover, the configuration of the decay heat removal system has been investigated considering sufficient utilization of natural circulation capability of sodium coolant, heat removal capacity of each cooling system, conformance with design requirements, and recommendations of SDC and SDG such as diversity and redundancy of components.
format	article
author	Shigenobu KUBO Yoshitaka CHIKAZAWA Hiroyuki OHSHIMA Masato UCHITA Takayuki MIYAGAWA Masao ETO Tetsuji SUZUNO Ichiyo MATOBA Junji ENDO Osamu WATANABE Koichi HIGURASHI
author_facet	Shigenobu KUBO Yoshitaka CHIKAZAWA Hiroyuki OHSHIMA Masato UCHITA Takayuki MIYAGAWA Masao ETO Tetsuji SUZUNO Ichiyo MATOBA Junji ENDO Osamu WATANABE Koichi HIGURASHI
author_sort	Shigenobu KUBO
title	A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
title_short	A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
title_full	A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
title_fullStr	A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
title_full_unstemmed	A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
title_sort	conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/123804690f6b4f56881dc87796cf6a72
work_keys_str_mv	AT shigenobukubo aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT yoshitakachikazawa aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT hiroyukiohshima aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT masatouchita aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT takayukimiyagawa aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT masaoeto aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT tetsujisuzuno aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT ichiyomatoba aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT junjiendo aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT osamuwatanabe aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT koichihigurashi aconceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT shigenobukubo conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT yoshitakachikazawa conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT hiroyukiohshima conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT masatouchita conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT takayukimiyagawa conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT masaoeto conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT tetsujisuzuno conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT ichiyomatoba conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT junjiendo conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT osamuwatanabe conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability AT koichihigurashi conceptualdesignstudyofpooltypesodiumcooledfastreactorwithenhancedantiseismiccapability
_version_	1718407568962879488

A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Ejemplares similares