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Analysis of radionuclide release through EBS of conceptual repository for Lithuanian RBMK spent nuclear fuel disposal : case of canister with initial defect

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
This paper presents research on radionuclide transport from generic geological repository for the RBMK-1500 SNF of 2.8 235U initial enrichment (with Er absorber) and average burn-up of ~ 29 MWd/kgU. Radionuclide transport analysis was focused on the engineered barrier system (EBS) and performed taking into account possible differences in the data on the initial size of a canister defect, defect enlargement time and radionuclide release start time. For the numerical simulations, computer code AMBER (UK) was used. The analysis of radionuclide transport regularities demonstrates that the release from the EBS is the most intensive after the defect enlargement. Most relevant radionuclides were identified based on the mass transfer analysis complemented by the analysis of radiotoxicity flux. The results showed that, depending on the differences of the initial defect size, defect enlargement time and release start time, the peak flux from the EBS may vary by a factor of 2 (for 129I) and 1.5 (for 226Ra) for RBMK-1500 SNF.
Czasopismo
Rocznik
Strony
487--495
Opis fizyczny
Bibliogr. 26 poz., rys.
Twórcy
autor
  • Nuclear Engineering Laboratory, Lithuanian Energy Institute, 3 Breslaujos Str., LT-44403 Kaunas, Lithuania, Tel.: +370 37 401 886, Fax: +370 37 351 271
  • Nuclear Engineering Laboratory, Lithuanian Energy Institute, 3 Breslaujos Str., LT-44403 Kaunas, Lithuania, Tel.: +370 37 401 886, Fax: +370 37 351 271
  • Nuclear Engineering Laboratory, Lithuanian Energy Institute, 3 Breslaujos Str., LT-44403 Kaunas, Lithuania, Tel.: +370 37 401 886, Fax: +370 37 351 271
autor
  • Nuclear Engineering Laboratory, Lithuanian Energy Institute, 3 Breslaujos Str., LT-44403 Kaunas, Lithuania, Tel.: +370 37 401 886, Fax: +370 37 351 271
Bibliografia
  • 1. Apted MJ (1990) Radionuclide release from high--level nuclear waste packages. J Radioanal Nucl Chem 142:321–330
  • 2. Brazauskaite A, Poskas P (2006) Modelling of radionuclide releases from the near field of the geological repository in crystalline rocks for RBMK-1500 spent nuclear fuel. In: Proc of the Int Topical Meeting TOPSEAL 2006, 17–20 September 2006, Olkiluoto, Finland
  • 3. Brazauskaite A, Poskas P (2006) Radionuclide migration from the geological repository of the RBMK-1500 spent nuclear fuel in crystalline rocks. 2. Identification of safety relevant radionuclides. Power Engineering 2:47–56 (in Lithuanian)
  • 4. Broczkowski ME, Noel JJ, Shoesmith DW (2005) The inhibiting effects of hydrogen on the corrosion of uranium dioxide under nuclear waste disposal conditions. J Nucl Mater 346:16–23
  • 5. Enviros Quintessa (2002) AMBER 4.4. Getting started, Version 1.0/ User’s manual 6. European Communities (2005) Treatment of radionuclide transport in geosphere within safety assessments (RETROCK). EUR 21230 EN. Brussels
  • 7. European Union (2011) Council Directive 2011/70/Euratom of 19 July 2011. Establishing a Community framework
  • for the responsible and safe management of spent fuel and radioactive waste. Brussels
  • 8. Ferry C, Poinssot C, Cappelaere C et al. (2006) Specific outcomes of the research on the spent fuel long-term evolution in interim dry storage and deep geological disposal. J Nucl Mater 352:246–253
  • 9. Granbow B, Ferry C, Casas I et al. (2010) Spent fuel waste disposal: analyses of model uncertainty in the MICADO project. Energy Procedia 7:487–494
  • 10. IAEA (2009) Safety assessment for facilities and activities for protecting people and the environment. General Safety Requirements, no. GSR Part. 4. International Atomic Energy Agency, Vienna
  • 11. Johnson L, Ferry C, Poinssot C et al. (2005) Spent fuel radionuclide source-term model for assessing spent fuel performance in geological disposal. Part I. Assessment of the instant release fraction. J Nucl Mater 346:56–65
  • 12. Nordman H, Vieno T (2004) Equivalent flow rates from canister interior into the geosphere in a KBS-3H type repository. Report 2004-06. Posiva Oy, Finland
  • 13. Ochs M, Talerico C (2004) Data and uncertainty assessment. Migration parameters for the bentonite buffer in he KBS-3 concept. TR-04-18. SKB, Stockholm
  • 14. Poskas P, Adomaitis JE, Ragaisis V et al. (2012) Progress of radioactive waste management in Lithuania. Progr Nucl Energ 54:11–21
  • 15. Poskas P, Brazauskaite A (2007) Modeling of radionuclide releases from the geological repository for RBMK-1500 spent nuclear fuel in crystalline rocks in Lithuania. In: Proc of the 11th Int Conf ICEM2007, Bruges, Belgium
  • 16. Poskas P, Brazauskaite A, Narkunas E et al. (2006) Generic repository concept for RBMK-1500 spent nuclear fuel disposal in crystalline rocks in Lithuania. In: Proc of the Int Topical Meeting TOPSEAL 2006, 17–20 September 2006, Olkiluoto, Finland
  • 17. Pusch R (2006) The performance of clay barriers in repositories for high-level radioactive waste. Nucl Eng Technol 38;6:483–488
  • 18. Pusch R, Yong RN, Nakano M (2011) High-level radioactive waste (HLW) disposal: A global challenge. WIT Press, Southampton/GB, p 320
  • 19. Resolution no. 860 (2008) On approval of the strategy for management of radioactive waste, Government of Lithuania
  • 20. Romero L, Moreno L, Neretnieks I (1995) Fast multiple path model to calculate radionuclide release from the near field of a repository. Nucl Technol 112:89–98
  • 21. SKB (1999) Deep repository for spent nuclear fuel. SR-97 – Post-closure safety, TR-99-06. SKB, Stockholm
  • 22. SKB (1999) SR-97. Radionuclide transport calculations, TR-99-23. SKB, Stockholm
  • 23. SKB (2004) Interim main report of the safety assessment SR-Can, TR-04-11. SKB, Stockholm
  • 24. Smaizys A, Poskas P, Narkunas E (2010) Evaluation of nuclear and radiation characteristics of steel disposal canister for RBMK-1500 spent nuclear fuel. Power Engineering 56:173–177 (in Lithuanian)
  • 25. Vieno T, Nordman H (1999) Safety assessment of spent fuel disposal in Hästholmen, Kivetty, Olkiluoto and Romuvaara, TILA-99, Report 99-07, Posiva Oy, Finland
  • 26. Werme L, Johnson LH, Oversby VM et al. (2004) Spent fuel performance under repository conditions: A model for use in SR-Can, TR-04-19. SKB, Stockholm
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-0a6b57d9-9a46-41d6-998b-870fca059488
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