Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -

To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconi...

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Autores principales: Shohei UETA, Jun AIHARA, Minoru GOTO, Yukio TACHIBANA, Koji OKAMOTO
Formato: article
Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2018
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Acceso en línea:https://doaj.org/article/f82cdc398d9e471c9703ef6af6914994
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spelling oai:doaj.org-article:f82cdc398d9e471c9703ef6af69149942021-11-26T07:23:09ZDevelopment of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -2187-974510.1299/mej.18-00084https://doaj.org/article/f82cdc398d9e471c9703ef6af69149942018-09-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/5/5/5_18-00084/_pdf/-char/enhttps://doaj.org/toc/2187-9745To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy kernel made of YSZ which surrogates PuO2-YSZ have been started in the Japanese fiscal year 2015. As results of ZrC coating tests on YSZ particle by the bromide process developed in Japan Atomic Energy Agency, stoichiometric ZrC coatings with 18 - 21 μm of thicknesses were obtained with 0.1 kg of particle loading weight. As indicated by a thermochemical analysis on the chemical stability of YSZ against the ZrC bromide process, no deterioration of YSZ exposed by source gases of ZrC bromide process was observed through the characterization by Scanning Transmission Electron Microscope (STEM) observation. Finally, reproducibility of stoichiometric ZrC coating on YSZ particle was demonstrated by the bromide chemical vapor deposition process.Shohei UETAJun AIHARAMinoru GOTOYukio TACHIBANAKoji OKAMOTOThe Japan Society of Mechanical Engineersarticlecoated fuel particlezirconium carbidechemical vapor depositioncoating processcharacterizationMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 5, Iss 5, Pp 18-00084-18-00084 (2018)
institution DOAJ
collection DOAJ
language EN
topic coated fuel particle
zirconium carbide
chemical vapor deposition
coating process
characterization
Mechanical engineering and machinery
TJ1-1570
spellingShingle coated fuel particle
zirconium carbide
chemical vapor deposition
coating process
characterization
Mechanical engineering and machinery
TJ1-1570
Shohei UETA
Jun AIHARA
Minoru GOTO
Yukio TACHIBANA
Koji OKAMOTO
Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
description To develop Pu-burner high temperature gas-cooled reactor (HTGR) attaining very high burn-up around 500 GWd/t, the security and safety fuel (3S-TRISO fuel) is proposed. The 3S-TRISO fuel employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO2) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy kernel made of YSZ which surrogates PuO2-YSZ have been started in the Japanese fiscal year 2015. As results of ZrC coating tests on YSZ particle by the bromide process developed in Japan Atomic Energy Agency, stoichiometric ZrC coatings with 18 - 21 μm of thicknesses were obtained with 0.1 kg of particle loading weight. As indicated by a thermochemical analysis on the chemical stability of YSZ against the ZrC bromide process, no deterioration of YSZ exposed by source gases of ZrC bromide process was observed through the characterization by Scanning Transmission Electron Microscope (STEM) observation. Finally, reproducibility of stoichiometric ZrC coating on YSZ particle was demonstrated by the bromide chemical vapor deposition process.
format article
author Shohei UETA
Jun AIHARA
Minoru GOTO
Yukio TACHIBANA
Koji OKAMOTO
author_facet Shohei UETA
Jun AIHARA
Minoru GOTO
Yukio TACHIBANA
Koji OKAMOTO
author_sort Shohei UETA
title Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
title_short Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
title_full Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
title_fullStr Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
title_full_unstemmed Development of security and safety fuel for Pu-burner HTGR - Test and characterization for ZrC coating -
title_sort development of security and safety fuel for pu-burner htgr - test and characterization for zrc coating -
publisher The Japan Society of Mechanical Engineers
publishDate 2018
url https://doaj.org/article/f82cdc398d9e471c9703ef6af6914994
work_keys_str_mv AT shoheiueta developmentofsecurityandsafetyfuelforpuburnerhtgrtestandcharacterizationforzrccoating
AT junaihara developmentofsecurityandsafetyfuelforpuburnerhtgrtestandcharacterizationforzrccoating
AT minorugoto developmentofsecurityandsafetyfuelforpuburnerhtgrtestandcharacterizationforzrccoating
AT yukiotachibana developmentofsecurityandsafetyfuelforpuburnerhtgrtestandcharacterizationforzrccoating
AT kojiokamoto developmentofsecurityandsafetyfuelforpuburnerhtgrtestandcharacterizationforzrccoating
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