Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium

  • Md Akhlak Bin Aziz Military Institute of Science and Technology, Dhaka
  • Afrin Ahsan Military Institute of Science and Technology, Dhaka
  • Md Monsurul Islam Khan Indiana University Purdue University Indianapolis, India
  • Zahid Hasan Mahmood University of Dhaka, Dhaka
Keywords: Nuclear Spent Fuel, Fission Product, UNEX process, Waste Immobilization

Abstract

Separation of heat generating, high level fission product caesium and strontium from spent nuclear fuel boosts the capacity of waste repositories by as much as fifty times. For efficient use of already scarce repositories, separation of such fission products is mandatory. Separations of caesium and strontium using Chlorinated Cobalt Dicarbollide (CCD), PEG (Polyethylene Glycol), UNEX process and by Calixarenes or Fission Product Extraction Process (FPEX) were discussed. The UNEX method was then proposed as the most feasible method option. Following separation, nuclear waste immobilization techniques for such high-level fission product were discussed. The techniques included usage of concrete, glass and synthetic rock. Among them synthetic rock was identified as the most suitable one for immobilization of high-level nuclear waste. Finally, a safe disposal system with necessary required geology was shown for safe disposal of the waste.

Journal of Chemical Engineering, Vol. 30, No. 1, 2017: 37-42

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Abstract
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PDF
1059
Published
2017-12-07
How to Cite
Aziz, M. A., Ahsan, A., Khan, M. M., & Mahmood, Z. (2017). Treatment of Spent Nuclear Fuel for Separation, Immobilization and Disposal of Heat Generating High Level Fission Products, Caesium and Strontium. Journal of Chemical Engineering, 30(1), 37-42. https://doi.org/10.3329/jce.v30i1.34796
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Articles