Paper Title:
Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant
  Abstract

I-129 is a very long-lived radionuclide that is released to an off-gas stream when spent fuels are dissolved at a reprocessing plant. An iodine filter can capture I-129 in the form of AgI. However, because AgI is unstable under the reducing conditions of a geological repository and I-129 has a very long half-life, I-129 can migrate to the biosphere. These characteristics make I-129 a key radionuclide for the safety assessment of a geological disposal of radioactive wastes generated from a reprocessing plant (TRU wastes). To improve disposal safety, several new waste forms have been developed to confine I-129 for a very long period in order to reduce the leaching of I-129 from radioactive wastes. These new waste forms have technical objectives of solidifying more than 95% of I-129 into the waste form and achieving a leaching rate of less than 10-5/y. Several iodine immobilization techniques have been examined. This paper presents experimental results concerning the treatment process, leaching behavior, modeling, and related elements of these immobilization techniques.

  Info
Periodical
Edited by
Pietro VINCENZINI, Hua-Tay LIN and Kevin FOX
Pages
158-170
DOI
10.4028/www.scientific.net/AST.73.158
Citation
H. Tanabe, T. Sakuragi, K. Yamaguchi, T. Sato, H. Owada, "Development of New Waste Forms to Immobilize Iodine-129 Released from a Spent Fuel Reprocessing Plant", Advances in Science and Technology, Vol. 73, pp. 158-170, 2010
Online since
October 2010
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