Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel

To reduce the environmental burden caused by the disposal of spent nuclear fuel, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute. The technology includes a nuclide management process that can maximize disposal efficiency by selectively...

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Main Authors: Jung-Hoon Choi, Byeonggwan Lee, Ki-Rak Lee, Hyun Woo Kang, Hyeon Jin Eom, Seong-Sik Shin, Ga-Yeong Kim, Hwan-Seo Park
Format: Article
Language:English
Published: Wiley 2022-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2022/4764825
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author Jung-Hoon Choi
Byeonggwan Lee
Ki-Rak Lee
Hyun Woo Kang
Hyeon Jin Eom
Seong-Sik Shin
Ga-Yeong Kim
Hwan-Seo Park
author_facet Jung-Hoon Choi
Byeonggwan Lee
Ki-Rak Lee
Hyun Woo Kang
Hyeon Jin Eom
Seong-Sik Shin
Ga-Yeong Kim
Hwan-Seo Park
author_sort Jung-Hoon Choi
collection DOAJ
description To reduce the environmental burden caused by the disposal of spent nuclear fuel, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute. The technology includes a nuclide management process that can maximize disposal efficiency by selectively separating and collecting major nuclides in spent nuclear fuel. To manufacture a waste form of high durability, the characteristics of the waste generated during the process should be evaluated. In this study, the physical, radiological, and thermal characteristics of the waste and waste forms for major nuclides (Cs, Sr, I, transuranic/rare earth, and Tc/Se) generated in the nuclide management process were analyzed. In the case of Cs nuclides, characterization was conducted according to the capture rate of the adsorbent in the high-temperature heat treatment process; meanwhile, in the case of Sr nuclides, characterization was performed by considering the ratio of similar nuclides in the chlorination process. For I nuclide, analysis was performed based on the available waste form, and for TRU/RE and Tc/Se nuclides, analysis was performed by considering chlorination and mid-temperature heat treatment. The radioactivity and heat generation rate of each waste and waste form were evaluated over a period of 1,000 years. The results of this study could be used to derive the centerline temperature for the thermal stability evaluation of waste forms and for the feasibility evaluation of each disposal system considered in the waste burden minimization technology.
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spelling doaj-art-92234780b7e34728b0bb62c5de512ee42025-02-03T05:49:25ZengWileyScience and Technology of Nuclear Installations1687-60832022-01-01202210.1155/2022/4764825Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear FuelJung-Hoon Choi0Byeonggwan Lee1Ki-Rak Lee2Hyun Woo Kang3Hyeon Jin Eom4Seong-Sik Shin5Ga-Yeong Kim6Hwan-Seo Park7Radioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamRadioactive Waste Treatment Research TeamTo reduce the environmental burden caused by the disposal of spent nuclear fuel, waste burden minimization technology is currently being developed at the Korea Atomic Energy Research Institute. The technology includes a nuclide management process that can maximize disposal efficiency by selectively separating and collecting major nuclides in spent nuclear fuel. To manufacture a waste form of high durability, the characteristics of the waste generated during the process should be evaluated. In this study, the physical, radiological, and thermal characteristics of the waste and waste forms for major nuclides (Cs, Sr, I, transuranic/rare earth, and Tc/Se) generated in the nuclide management process were analyzed. In the case of Cs nuclides, characterization was conducted according to the capture rate of the adsorbent in the high-temperature heat treatment process; meanwhile, in the case of Sr nuclides, characterization was performed by considering the ratio of similar nuclides in the chlorination process. For I nuclide, analysis was performed based on the available waste form, and for TRU/RE and Tc/Se nuclides, analysis was performed by considering chlorination and mid-temperature heat treatment. The radioactivity and heat generation rate of each waste and waste form were evaluated over a period of 1,000 years. The results of this study could be used to derive the centerline temperature for the thermal stability evaluation of waste forms and for the feasibility evaluation of each disposal system considered in the waste burden minimization technology.http://dx.doi.org/10.1155/2022/4764825
spellingShingle Jung-Hoon Choi
Byeonggwan Lee
Ki-Rak Lee
Hyun Woo Kang
Hyeon Jin Eom
Seong-Sik Shin
Ga-Yeong Kim
Hwan-Seo Park
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
Science and Technology of Nuclear Installations
title Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
title_full Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
title_fullStr Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
title_full_unstemmed Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
title_short Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel
title_sort characterization of waste generated from nuclide management process in waste burden minimization technology for spent nuclear fuel
url http://dx.doi.org/10.1155/2022/4764825
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