Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating

SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-...
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Autor*in:	Zhao He [verfasserIn] Jinliang Song [verfasserIn] Pengfei Lian [verfasserIn] Dongqing Zhang [verfasserIn] Zhanjun Liu [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2019

Übergeordnetes Werk:	In: Nuclear Engineering and Technology - Elsevier, 2016, 51(2019), 5, Seite 1390-1397
Übergeordnetes Werk:	volume:51 ; year:2019 ; number:5 ; pages:1390-1397

Links:	Link aufrufen Link aufrufen Link aufrufen Journal toc

DOI / URN:	10.1016/j.net.2019.03.006

Katalog-ID:	DOAJ056795270

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520			\|a SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR. Keywords: Composite coating, Nuclear graphite, Molten salt reactor, Molten salt infiltration
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callnumber-first	T - Technology
author	Zhao He
spellingShingle	Zhao He misc TK9001-9401 misc Nuclear engineering. Atomic power Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
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topic_title	TK9001-9401 Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
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topic_unstemmed	misc TK9001-9401 misc Nuclear engineering. Atomic power
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title	Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
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title_full	Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
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author_browse	Zhao He Jinliang Song Pengfei Lian Dongqing Zhang Zhanjun Liu
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doi_str_mv	10.1016/j.net.2019.03.006
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title_sort	excluding molten fluoride salt from nuclear graphite by sic/glassy carbon composite coating
callnumber	TK9001-9401
title_auth	Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
abstract	SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR. Keywords: Composite coating, Nuclear graphite, Molten salt reactor, Molten salt infiltration
abstractGer	SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR. Keywords: Composite coating, Nuclear graphite, Molten salt reactor, Molten salt infiltration
abstract_unstemmed	SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR. Keywords: Composite coating, Nuclear graphite, Molten salt reactor, Molten salt infiltration
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container_issue	5
title_short	Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating
url	https://doi.org/10.1016/j.net.2019.03.006 https://doaj.org/article/9f011115d9c44ba6abdc3bc8371a1fc0 http://www.sciencedirect.com/science/article/pii/S1738573318307046 https://doaj.org/toc/1738-5733
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author2	Jinliang Song Pengfei Lian Dongqing Zhang Zhanjun Liu
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up_date	2024-07-03T22:53:18.215Z
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Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating

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