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.
Government gave land and housing to evacuees and an additional USD $1030 per month for psychological suffering. But evacuees were not allowed to return to regions with radiation of 20-50 mSv/y despite IAEA effective dose limit for one year being 50 mSv. Moreover, dose limit for clean up workers were also set at 250 mSv compared to international allowable limit of 500 mSv. Post accidents efforts taken by the government were praiseworthy but a less conservative limit to allow return of evacuees could have saved a lot more people.
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