Melting and draining tests on glass waste form for the immobilization of Cs, Sr, and rare-earth nuclides using a cold-crucible induction melting system

  • Choi, Jung-Hoon; 
  • Lee, Byeonggwan; 
  • Lee, Ki-Rak; 
  • Kang, Hyun Woo; 
  • Eom, Hyeon Jin; 
  • 외 1명
Citations

WEB OF SCIENCE

5
Citations

SCOPUS

7

초록

Cold-crucible induction melting (CCIM) technology has been intensively studied as an advanced vitrification process for the immobilization of highly radioactive waste. This technology uses high-frequency induction to melt a glass matrix and waste, while the outer surface of the crucible is water-cooled, resulting in the formation of a frozen glass layer (skull). In this study, for the fabrication of borosilicate glass waste form, CCIM operation test with 60 kg of glass per batch was conducted using surrogate wastes composed of Cs, Sr, and Nd as a representative of highly radioactive nuclides generated during spent nuclear fuel management. A 60 kg-scale glass waste form was successfully fabricated through melting and draining processes using a CCIM system, and its physicochemical properties were analyzed. In particular, to enhance the controllability and reliability of the draining process, an air-cooling drain control method that can control draining through air-cooling near drain holes was developed, and its validity for draining control was verified. The method can offer controllability on various draining processes, such as molten salt or molten metal draining processes, and can be applied to a process requiring high throughput draining. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

키워드

Cold-crucible induction melting; CCIM; Glass waste form; Immobilization; Vitri fication; Highly radioactive waste; Glass melt draining
제목
Melting and draining tests on glass waste form for the immobilization of Cs, Sr, and rare-earth nuclides using a cold-crucible induction melting system
저자
Choi, Jung-Hoon; Lee, Byeonggwan; Lee, Ki-Rak; Kang, Hyun Woo; Eom, Hyeon Jin; Park, Hwan-Seo
DOI
10.1016/j.net.2021.09.041
발행일
2022-04
유형
Article
저널명
Nuclear Engineering and Technology
권
54
호
4
페이지
1206 ~ 1212