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Solidification of Simulated Liquid Waste of Primary Loop Resin Elution Process of PWR

[+] Author Affiliations
Masamichi Obata, Nobuhito Ogaki, Taichi Horimoto

Toshiba Corporation, Yokohama, Kanagawa, Japan

Masaaki Kaneko, Michitaka Saso

Toshiba Corporation, Kawasaki, Kanagawa, Japan

Toshikazu Waki

The Kansai Electric Power Company, Osaka, Osaka, Japan

Paper No. ICEM2010-40026, pp. 41-44; 4 pages
doi:10.1115/ICEM2010-40026
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

Primary loop resin waste is eluted by sulfuric acid in The Kansai Electic Company Mihama, Takahama and Ohi nuclear power station. Waste solution from this elution process is planned to be solidified by cement. This study bring out a range of chemical composition and crud concentration of waste solution from this elution process, and examine the properties of alumina cement solidification process and solidified material. Test for sulfate ion, borate, lithium, ammonium ion was carried out. Volume reduction ratio of over 0.5 was achieved for 5 to 25wt% of sulfate ion and <5,000ppm of borate. Lithium ion restrained the solidification delay by borate. Also, ammonium ion shows no significant effect. Based on this study, we concluded that the aluminum cement is applicable to all range of composition of waste solution from the resin elution process. This study is a part of committed work of The Kansai electric company.

Copyright © 2010 by ASME

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