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Immobilization of Spent Ion Exchange Resins from Bushehr Nuclear Power Plant

Bamshad, Zahra | 2018

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 50837 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Samadfam, Mohammad; Davarkhah, Reza; Tavasoli, Maryam
  7. Abstract:
  8. Ion exchange resins are widely used in nuclear industries. These spent resins result in the production of a large amount of low and intermediate level radioactive wastes, therefore, the treatment and immobilization of spent ion exchange resins are the major problems in the development of nuclear power plants.In this research, in a laboratory scale, we tried to find the suitable procedure and formulation to immobilize a specific group of cation-exchange resins which is used in Bushehr nuclear power plant (AMBERLITE IRN-97H) in the cement matrix. The solidification matrix consists of five constituents: anti sulfate slag type portland cement, cation-exchange resins, diatomite, sodium hydroxide and water.The first set of experiments are carried out to optimize the amount of diatomite additive. Thus, the cement mortar samples were prepared in different amounts of diatomite varying from 0% to 8%, in three water to cement ratios, 0.35, 0.40 and 0.50 and their setting times were determined. After 28 days of curing, compressive strength and leaching tests were carried out. Results indicated that with the addition of 4% (W/W) diatomite, the acceptance criterion for compressive strength, which is 5 MPa or higher was satisfied and the setting times of samples were less than the usual operational limit i.e. 24 hours. What’s more, by adding the optimum amount of diatomite, the cumulative leach fraction of Cs ion was kept at the lowest value. In the second part of this study, the experiments were performed to optimize the loading amount of cation-exchange resins in the immobilization matrix. While diatomite was maintained at its optimum value, the weight percentage of resins was varied between 7% to 18% in the matrix. In spite of the fact that the compressive strength of the cured specimens after 28 days satisfied the limits of waste acceptance criteria, for resin loadings higher than 9 weight percent, more than 80% of Cs ions present in the specimens was leached out in just after 19 days
  9. Keywords:
  10. Radioactive Waste ; Ion Exchange Resines ; Immobilization ; Diatomic Soil ; Bushehr Nuclear Power Plant ; Immobilization in Cement Matrix

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