Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt

Considering the necessity of the development of methods to reduce the burden of storage and disposal of high-level radioactive waste, in this study, we propose a nuclide separation technique using molten salt immersion. The dissolution behavior of simulated spent nuclear fuels (SSFs) immersed in a L...

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Autores principales:	Sang-Kwon Lee, Sung-Wook Kim, Jun-Hyuk Jang, Min Ku Jeon, Eun-Young Choi
Formato:	article
Lenguaje:	EN
Publicado:	Hindawi Limited 2021
Materias:	Electrical engineering. Electronics. Nuclear engineering TK1-9971
Acceso en línea:	https://doaj.org/article/d4a7c0da54ab4d5ea6e68b349f9970f3
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spelling	oai:doaj.org-article:d4a7c0da54ab4d5ea6e68b349f9970f32021-11-15T01:19:56ZDissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt1687-608310.1155/2021/9048775https://doaj.org/article/d4a7c0da54ab4d5ea6e68b349f9970f32021-01-01T00:00:00Zhttp://dx.doi.org/10.1155/2021/9048775https://doaj.org/toc/1687-6083Considering the necessity of the development of methods to reduce the burden of storage and disposal of high-level radioactive waste, in this study, we propose a nuclide separation technique using molten salt immersion. The dissolution behavior of simulated spent nuclear fuels (SSFs) immersed in a LiCl-KCl-UCl3 (LKU) molten salt at 500°C was investigated using a combination of thermodynamic and experimental studies. Surrogates of transuranic elements (TRUs), that is, rare earth elements (REs), in the SSFs were dissolved into the molten salt without any damage to the UO2 structure of the SSFs. The results suggest that the LKU salt technique can be used to separate REs and, potentially, TRUs from actual spent nuclear fuels (SNFs). It is thought that this technique is advantageous over the conventional TRU recovery techniques because the majority of the SNFs (i.e., UO2) remained stable, thus reducing the process burden. Several SNF treatment process options using this technique were suggested. This study will serve as a guide for future studies on the management of high-level waste discharged from nuclear reactors.Sang-Kwon LeeSung-Wook KimJun-Hyuk JangMin Ku JeonEun-Young ChoiHindawi LimitedarticleElectrical engineering. Electronics. Nuclear engineeringTK1-9971ENScience and Technology of Nuclear Installations, Vol 2021 (2021)
institution	DOAJ
collection	DOAJ
language	EN
topic	Electrical engineering. Electronics. Nuclear engineering TK1-9971
spellingShingle	Electrical engineering. Electronics. Nuclear engineering TK1-9971 Sang-Kwon Lee Sung-Wook Kim Jun-Hyuk Jang Min Ku Jeon Eun-Young Choi Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
description	Considering the necessity of the development of methods to reduce the burden of storage and disposal of high-level radioactive waste, in this study, we propose a nuclide separation technique using molten salt immersion. The dissolution behavior of simulated spent nuclear fuels (SSFs) immersed in a LiCl-KCl-UCl3 (LKU) molten salt at 500°C was investigated using a combination of thermodynamic and experimental studies. Surrogates of transuranic elements (TRUs), that is, rare earth elements (REs), in the SSFs were dissolved into the molten salt without any damage to the UO2 structure of the SSFs. The results suggest that the LKU salt technique can be used to separate REs and, potentially, TRUs from actual spent nuclear fuels (SNFs). It is thought that this technique is advantageous over the conventional TRU recovery techniques because the majority of the SNFs (i.e., UO2) remained stable, thus reducing the process burden. Several SNF treatment process options using this technique were suggested. This study will serve as a guide for future studies on the management of high-level waste discharged from nuclear reactors.
format	article
author	Sang-Kwon Lee Sung-Wook Kim Jun-Hyuk Jang Min Ku Jeon Eun-Young Choi
author_facet	Sang-Kwon Lee Sung-Wook Kim Jun-Hyuk Jang Min Ku Jeon Eun-Young Choi
author_sort	Sang-Kwon Lee
title	Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
title_short	Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
title_full	Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
title_fullStr	Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
title_full_unstemmed	Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt
title_sort	dissolution behavior of simulated spent nuclear fuel in licl-kcl-ucl3 molten salt
publisher	Hindawi Limited
publishDate	2021
url	https://doaj.org/article/d4a7c0da54ab4d5ea6e68b349f9970f3
work_keys_str_mv	AT sangkwonlee dissolutionbehaviorofsimulatedspentnuclearfuelinliclkclucl3moltensalt AT sungwookkim dissolutionbehaviorofsimulatedspentnuclearfuelinliclkclucl3moltensalt AT junhyukjang dissolutionbehaviorofsimulatedspentnuclearfuelinliclkclucl3moltensalt AT minkujeon dissolutionbehaviorofsimulatedspentnuclearfuelinliclkclucl3moltensalt AT eunyoungchoi dissolutionbehaviorofsimulatedspentnuclearfuelinliclkclucl3moltensalt
_version_	1718428951022403584

Dissolution Behavior of Simulated Spent Nuclear Fuel in LiCl-KCl-UCl3 Molten Salt

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