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Decommissioning Activities for Salaspils Research Reactor

[+] Author Affiliations
A. Abramenkovs

Latvian Environment, Geology and Meteorology Centre, Riga, Latvia

J. Malnacs

Ministry of Environment and Regional Development, State Environmental Service, Radiation Safety Centre, Riga, Latvia

Paper No. ICEM2011-59055, pp. 513-518; 6 pages
  • ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management
  • ASME 2011 14th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B
  • Reims, France, September 25–29, 2011
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 978-0-7918-5498-3
  • Copyright © 2011 by ASME


In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH at 1998–1999. The Latvian government decided to start the direct dismantling to “green field” in October 26, 1999. The upgrade of decommissioning and dismantling plan was performed in 2003–2004 years, which change the main goal of decommissioning to the “brown field”. The paper deals with the SRR decommissioning experience during 1999–2010. The main decommissioning stages are discussed including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning of nuclear facility. Radioactive waste management’s main efforts were devoted to collecting and conditioning of “historical” radioactive wastes from different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers for disposal in the radioactive wastes repository “Radons” at Baldone site. The dismantling of contaminated and activated components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed. Infrastructure of SRR, including personal protective and radiation measurement equipment, for decommissioning purposes was upgraded significantly. Additional attention was devoted to the free release measurement’s technique. The certified laboratory was installed for supporting of all decommissioning activities. All non-radioactive equipments and materials outside of reactor buildings were released for clearance and dismantled for reusing or conventional disposing. Weakly contaminated materials from reactor hall were collected, decontaminated and removed for clearance measurements.

Copyright © 2011 by ASME



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