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Derivation Clearance Levels for Solid Radioactive Materials From Nuclear Installations Decommissioning

[+] Author Affiliations
Jozef Pritrsky

Decom, a.s., Trnava, Slovakia

Jana Frankovska

Slovak University of Technology in Bratislava, Bratislava, Slovakia

Paper No. ICONE20-POWER2012-54042, pp. 241-246; 6 pages
doi:10.1115/ICONE20-POWER2012-54042
From:
  • 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
  • Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes
  • Anaheim, California, USA, July 30–August 3, 2012
  • Conference Sponsors: Nuclear Engineering Division, Power Division
  • ISBN: 978-0-7918-4498-4
  • Copyright © 2012 by ASME

abstract

The paper presents the results of derivation clearance levels for solid radioactive materials from nuclear installations decommissioning. Assumed target value for a member of a critical group of public was 10 μSv/year (50 μSv/year for skin exposure), which is in compliance with national legislative documents. We elaborated a set of exposure scenarios for the considered release options and on this base we calculated the resulting individual and collective doses including the corresponding clearance levels for particular radionuclides. Main radionuclides release and migration mechanisms were investigated in details. For this purpose we compiled data, developed conceptual model and mathematical model. All exposure pathways (ingestion, inhalation, external exposure and skin exposure) were considered. GoldSim software has been used for the purpose of mathematical simulation. The criteria presented in the paper only apply to assumed practices, exposure scenarios and materials.

Copyright © 2012 by ASME

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