On the degradation progression of a BWR control blade under high-temperature steam-starved conditions

High-temperature control blade degradation tests simulating a beginning phase of a severe accident in BWRs has been comprehensively performed in Japan Atomic Energy Agency (JAEA). In the latest test, a mock-up of BWR bundle material has been investigated under postulated Fukushima Dai-Ichi (1F) unit...

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Autores principales:	Anton PSHENICHNIKOV, Yuji NAGAE, Masaki KURATA
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	boiling water reactor severe accident fukushima dai-ichi decommissioning control blade degradation boron carbide fuel debris Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/40f94824f5da4d49bf48827b2aeef709
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spelling	oai:doaj.org-article:40f94824f5da4d49bf48827b2aeef7092021-11-29T05:56:30ZOn the degradation progression of a BWR control blade under high-temperature steam-starved conditions2187-974510.1299/mej.19-00503https://doaj.org/article/40f94824f5da4d49bf48827b2aeef7092020-04-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/3/7_19-00503/_pdf/-char/enhttps://doaj.org/toc/2187-9745High-temperature control blade degradation tests simulating a beginning phase of a severe accident in BWRs has been comprehensively performed in Japan Atomic Energy Agency (JAEA). In the latest test, a mock-up of BWR bundle material has been investigated under postulated Fukushima Dai-Ichi (1F) unit 2 accident conditions in a complex heating transient scenario including a phase of lack of available steam. The progress in control blade degradation was monitored with help of an in situ video and the detailed analysis of the solidified metallic melt, so-called “metallic debris”, was carried out by conventional SEM EDS method. These results indicated that the composition of the metallic debris at different elevations has been significantly changed due to the redistribution and relocation of steel elements under the influence of B and C, sometimes accompanied by a formation of high-melting-point layers. The results of this paper significantly contribute to the physical understanding of control blade degradation phenomenology during beginning phase of a core degradation for a special case of steam-starved conditions at 1F unit 2.Anton PSHENICHNIKOVYuji NAGAEMasaki KURATAThe Japan Society of Mechanical Engineersarticleboiling water reactorsevere accidentfukushima dai-ichi decommissioningcontrol blade degradationboron carbidefuel debrisMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 3, Pp 19-00503-19-00503 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	boiling water reactor severe accident fukushima dai-ichi decommissioning control blade degradation boron carbide fuel debris Mechanical engineering and machinery TJ1-1570
spellingShingle	boiling water reactor severe accident fukushima dai-ichi decommissioning control blade degradation boron carbide fuel debris Mechanical engineering and machinery TJ1-1570 Anton PSHENICHNIKOV Yuji NAGAE Masaki KURATA On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
description	High-temperature control blade degradation tests simulating a beginning phase of a severe accident in BWRs has been comprehensively performed in Japan Atomic Energy Agency (JAEA). In the latest test, a mock-up of BWR bundle material has been investigated under postulated Fukushima Dai-Ichi (1F) unit 2 accident conditions in a complex heating transient scenario including a phase of lack of available steam. The progress in control blade degradation was monitored with help of an in situ video and the detailed analysis of the solidified metallic melt, so-called “metallic debris”, was carried out by conventional SEM EDS method. These results indicated that the composition of the metallic debris at different elevations has been significantly changed due to the redistribution and relocation of steel elements under the influence of B and C, sometimes accompanied by a formation of high-melting-point layers. The results of this paper significantly contribute to the physical understanding of control blade degradation phenomenology during beginning phase of a core degradation for a special case of steam-starved conditions at 1F unit 2.
format	article
author	Anton PSHENICHNIKOV Yuji NAGAE Masaki KURATA
author_facet	Anton PSHENICHNIKOV Yuji NAGAE Masaki KURATA
author_sort	Anton PSHENICHNIKOV
title	On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
title_short	On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
title_full	On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
title_fullStr	On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
title_full_unstemmed	On the degradation progression of a BWR control blade under high-temperature steam-starved conditions
title_sort	on the degradation progression of a bwr control blade under high-temperature steam-starved conditions
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/40f94824f5da4d49bf48827b2aeef709
work_keys_str_mv	AT antonpshenichnikov onthedegradationprogressionofabwrcontrolbladeunderhightemperaturesteamstarvedconditions AT yujinagae onthedegradationprogressionofabwrcontrolbladeunderhightemperaturesteamstarvedconditions AT masakikurata onthedegradationprogressionofabwrcontrolbladeunderhightemperaturesteamstarvedconditions
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On the degradation progression of a BWR control blade under high-temperature steam-starved conditions

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