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Decontamination of Radioactive Concrete Wastes by Thermal and Mechanical Processes

[+] Author Affiliations
Byung Youn Min, Wang Kyu Choi, Ki Won Lee, Kune Woo Lee, Un Soo Chung

KAERI - Korea Atomic Energy Research Institute, Daejeon, Republic of Korea

Paper No. ICEM2010-40221, pp. 189-192; 4 pages
doi:10.1115/ICEM2010-40221
From:
  • ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management
  • ASME 2010 13th International Conference on Environmental Remediation and Radioactive Waste Management, Volume 1
  • Tsukuba, Japan, October 3–7, 2010
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 978-0-7918-5452-5 | eISBN: 978-0-7918-3888-4
  • Copyright © 2010 by ASME

abstract

The purpose of this paper is to provide the results of a series of volume reduction tests conducted in thermal and mechanical processes. The Korea Atomic Energy Research Institutes (KAERI) has developed volume reduction technology applicable to an activated heavy concrete waste generated by dismantling the South Korea Research Reactor (KRR-2) and the uranium-contaminated light weight concrete produced from a uranium conversion plant (UCP). The volume reduction rate could achieve above 70% by heating following a mechanical separation process. Demonstration tests were performed with concrete waste generated from KRR-2 and UCP by thermal and mechanical process. The developed processes were quite effective for the volume reduction of radioactively contaminated dismantled concrete waste.

Copyright © 2010 by ASME

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