Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing

The molten salt waste produced by disposal of spent fuel via molten salt electrolysis is classified as high-level waste. Because of high water solubility, complex elemental composition, high radioactivity, strong corrosiveness and high volatility, the nuclear waste forms used to immobilize molten sa...

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Main Authors: GAO Bei-bei, TANG Hao, SHAO Lang, CHU Ming-fu
Format: Article
Language:zho
Published: Editorial Office of Journal of Nuclear and Radiochemistry 2022-04-01
Series:He huaxue yu fangshe huaxue
Subjects:
Online Access:http://www.jnrc.org.cn/CN/10.7538/hhx.2022.YX.2020039
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author GAO Bei-bei
TANG Hao
SHAO Lang
CHU Ming-fu
author_facet GAO Bei-bei
TANG Hao
SHAO Lang
CHU Ming-fu
author_sort GAO Bei-bei
collection DOAJ
description The molten salt waste produced by disposal of spent fuel via molten salt electrolysis is classified as high-level waste. Because of high water solubility, complex elemental composition, high radioactivity, strong corrosiveness and high volatility, the nuclear waste forms used to immobilize molten salt waste needs to be thermal and chemical stabilities and irradiation resistance, which forms a stable leaching-resistant nuclear waste to isolate from the human living environment. Due to low compatibility with chloride, conventional silicate glass cannot be directly used to immobilize molten salt waste. Therefore, a great deal of research is focused on finding new suitable waste forms. This paper reviewed the treatment and disposal methods of chlorine-containing molten salt waste generated from reprocessing of spent fuel at home and abroad. There might be two routes to deal with chlorine-containing molten salt: the first one is to find a suitable host matrix for direct solidification, and common substrates are sodalite, apatite or phosphate glass; the second one is to convert the chloride to other forms of compounds, such as phosphates and oxides, followed by solidification. In view of the fact that China’s research in this field started late, this paper summarizes the chloride molten salt waste treatment and disposal methods that have been developed domestically and internationally, and introduces the principles, routes, and performance characteristics of each method.
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spelling doaj.art-ca3fa6d9d55648bf9e7ddd84e12755a82024-04-06T05:48:46ZzhoEditorial Office of Journal of Nuclear and RadiochemistryHe huaxue yu fangshe huaxue0253-99502022-04-0144215916910.7538/hhx.2022.YX.2020039Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry ReprocessingGAO Bei-bei0TANG Hao1SHAO Lang2CHU Ming-fu3Institute of Materials, China Academy of Engineering PhysicsInstitute of Materials, China Academy of Engineering PhysicsInstitute of Materials, China Academy of Engineering PhysicsInstitute of Materials, China Academy of Engineering PhysicsThe molten salt waste produced by disposal of spent fuel via molten salt electrolysis is classified as high-level waste. Because of high water solubility, complex elemental composition, high radioactivity, strong corrosiveness and high volatility, the nuclear waste forms used to immobilize molten salt waste needs to be thermal and chemical stabilities and irradiation resistance, which forms a stable leaching-resistant nuclear waste to isolate from the human living environment. Due to low compatibility with chloride, conventional silicate glass cannot be directly used to immobilize molten salt waste. Therefore, a great deal of research is focused on finding new suitable waste forms. This paper reviewed the treatment and disposal methods of chlorine-containing molten salt waste generated from reprocessing of spent fuel at home and abroad. There might be two routes to deal with chlorine-containing molten salt: the first one is to find a suitable host matrix for direct solidification, and common substrates are sodalite, apatite or phosphate glass; the second one is to convert the chloride to other forms of compounds, such as phosphates and oxides, followed by solidification. In view of the fact that China’s research in this field started late, this paper summarizes the chloride molten salt waste treatment and disposal methods that have been developed domestically and internationally, and introduces the principles, routes, and performance characteristics of each method.http://www.jnrc.org.cn/CN/10.7538/hhx.2022.YX.2020039spent fueldry reprocessingmolten salt wastechloridewaste disposal
spellingShingle GAO Bei-bei
TANG Hao
SHAO Lang
CHU Ming-fu
Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
He huaxue yu fangshe huaxue
spent fuel
dry reprocessing
molten salt waste
chloride
waste disposal
title Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
title_full Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
title_fullStr Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
title_full_unstemmed Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
title_short Review on Solidification of Chlorine-Containing Radioactive Molten Salt Waste From Dry Reprocessing
title_sort review on solidification of chlorine containing radioactive molten salt waste from dry reprocessing
topic spent fuel
dry reprocessing
molten salt waste
chloride
waste disposal
url http://www.jnrc.org.cn/CN/10.7538/hhx.2022.YX.2020039
work_keys_str_mv AT gaobeibei reviewonsolidificationofchlorinecontainingradioactivemoltensaltwastefromdryreprocessing
AT tanghao reviewonsolidificationofchlorinecontainingradioactivemoltensaltwastefromdryreprocessing
AT shaolang reviewonsolidificationofchlorinecontainingradioactivemoltensaltwastefromdryreprocessing
AT chumingfu reviewonsolidificationofchlorinecontainingradioactivemoltensaltwastefromdryreprocessing