Derivation of specific clearance levels for landfill disposed of waste at Ignalina NPP
Industrial waste generated from the operation of Ignalina Nuclear Power Plant (Ignalina NPP) was disposed of in industrial waste dumps , the so-called ‘landfill facility’. The Ignalina NPP's final decommissioning plan foresees the development of specific clearance levels for the disposed waste. The application of specific clearance would allow the removal of the waste from regulatory control and the conversion of the existing landfill into a conventional waste disposal facility. This paper describes and discusses scenarios, models, and parameter values that are used to derive specific clearance levels for the landfill disposed of waste at Ignalina NPP. The radionuclides considered in the assessment are based on the analysis of the waste specifics and include 3 H, 60 Co, 94 Nb, 137 Cs, and 241 Am. The derived specific clearance levels are higher than the corresponding generic clearance levels by approximately 3–27 times. • Specific clearance levels are derived for the landfill disposed of waste. • The radionuclides 3 H, 60 Co, 94 Nb and 137 Cs are considered. • Intrusion scenarios define values of the specific clearance levels. • Specific clearance levels exceed generic clearance levels by about 3–27 times.
Authors
- Povilas Poškas (ORCID: https://orcid.org/0000-0002-9723-502X)
- Audrius Šimonis (ORCID: https://orcid.org/0000-0003-1548-6253)
- Valdas Ragaišis (ORCID: https://orcid.org/0000-0002-0480-6162)
Institutions
- Lithuanian Energy Institute (LT)
Publication Details
- Journal
- Progress in Nuclear Energy
- Published
- 2025-05-01
- DOI
- https://doi.org/10.1016/j.pnucene.2025.105816
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 0.00