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Assessment of radionuclide migration and radiological human exposure at the closed near-surface radioactive waste repository

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
The near-surface “RADON” type radioactive waste repository, installed in 1963 and designed to store radioactive waste formed in industry, medicine and scientific investigations, was closed in 1989 because it did not meet the requirements imposed on the radioactive waste disposal. A comparatively small amount of radioactive waste is stored in this repository, but the inventory comprises various kinds of waste: short-lived low-level radioactive waste, short-lived low and intermediate radioactive waste, long-lived intermediate and high-level radioactive waste. The possible site-specific radionuclide migration through the groundwater pathway as well as the human exposure are considered by the computer program RESRAD-OFFSITE in this paper. The analysis of the obtained data shows that out of all stored radionuclides only H-3, C-14 and Cl-36 exceeding the dose constraint of 0.2 mSv can be considered as dangerous. The monitoring carried out in the repository environment has shown the contamination of groundwater with radioactive tritium and a significant reduction of contamination after construction of additional protective engineering barriers. For the assessment of the contribution of separate site-specific parameters of the model taking into account uncertainties of the model and parameters to the annual effective dose, the computer code RESRAD-OFFSITE provides the possibility of applying the regression analysis. It has been determined that the aquifer lateral dispersion as well as the hydraulic gradient, the radionuclide activity concentration in the repository together with the rate of penetration into the environment and the precipitation amount have the largest influence on the assessment accuracy of annual effective doses.
Czasopismo
Rocznik
Strony
251--259
Opis fizyczny
Bibliogr. 21 poz., rys.
Twórcy
autor
autor
  • Institute of Physics, 231 Savanoriu Ave., LT-02300, Vilnius, Lithuania, Tel.: +370 5 266 1643, Fax: +370 5 260 2317, gudelis@ktl.mii.lt
Bibliografia
  • 1. Filistovič V, Nedveckaitė T (2004) The investigation of effects of critical group size on the realibility of the mean annual individual dose using site-specific dietary parameter values. Sveikatos mokslai 14;2:8–12
  • 2. Galeriu D, Belot Y (2002) A standard guide for dose assessment of routine releases of tritium for any tritium facility. Report WP3 IDRANAP 31-01. Bucharest
  • 3. Hygiene Standard HN 87:2002 (2002) Radiation protection in nuclear facilities. Order no 643 on 17 December 2002 by the Lithuanian Minister of Health Care
  • 4. Improvement of Radiological Monitoring of the Maisiagala Radioactive Waste Repository (2006) Survey made by the CRIIRAD laboratory for THALES EC/PHARE project 632.06.01. CRIIRAD Draft Report no 06-23. Ed. Bruno Chareyron, Valence, France
  • 5. IAEA (2002) Maisiagala radioactive waste repository, Lithuania. IAEA DRCS. http://www-drsc.iaea.org/location. asp?siteid=8
  • 6. IAEA (2003) Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities. IAEA-TECDOC-1380. International Atomic Energy Agency, Vienna
  • 7. IAEA (2004) Derivation of quantitative acceptance criteria for disposal of radioactive waste to near surface facilities: development and implementation of an approach. International Atomic Energy Agency, Vienna
  • 8. IAEA (2004) Safety assessment methodologies for near surface disposal facilities results of a coordinated research project. Vol. 1. Review and enhancement of safety assessment approaches and tools. International Atomic Energy Agency, Vienna
  • 9. IAEA (2004) Safety assessment methodologies for near surface disposal facilities results of a coordinated research project. Vol. 2. Test cases. International Atomic Energy Agency, Vienna
  • 10. Jakimaviciute-Masiuliene V, Mazeika J, Petrosius R, Motiejūnas S (2004) Observations in the environment of Maisiagala storage facility and safety assessment. Sveikatos mokslai 14;2:28–33 (in Lithuanian)
  • 11. Kadziauskienė K (2000) Recommended daily alimentary products and energy rations. Lithuanian Republic Nutrition Centre, SOLIDARITY, Vilnius
  • 12. Krašto Projektai ir partneriai, Ltd. (2006) Maisiagala waste repository cover’s engineering barriers reconstruction. Technical project 1146-01. Vilnius
  • 13. Lithuanian Energy Institute (2004) Radionuclide inventory at Maišiagala repository. LEI Report no. S/14-625.4.6-G-V:01
  • 14. Mazeika J, Petrosius R, Jakimaviciute-Masiuliene V et al.(2003) Evaluation of processes and parameters governing radionuclide transfer in hydrogeological systems. Environ Chem Phys 25;4:191–201
  • 15. Mazeika J, Petrosius R, Jakimaviciute-Masiuliene V et al. (2008) Long-term safety assessment of a (near-surface) short-lived radioactive waste repository in Lithuania. Nucl Technol 161:1–13
  • 16. Meyer PD, Gee GW (1999) Information on hydrologic conceptual models, parameters, uncertainty analysis, and data sources for dose assessments at decommissioning sites. NUREG/CR-6656. US Nuclear Regulatory Commission, Washington, DC
  • 17. Ministry of Environment of the Republic of Lithuania (2007) Normative Document LAND 42-2007. Release of radionuclides into the environment from nuclear facilities and radioactive release limitation of permitting and radiological monitoring for approval. Official Gaz, no 138-5693
  • 18. RESRAD Family of Codes. http://www.ead.anl.gov/ resrad
  • 19. State Enterprise Radioactive Waste Management Agency (RATA) (2008) Maisiagala radioactive waste repository. http://www.rata.lt/en.php/maisiagala
  • 20. THALES, ANDRA, Institute of Physics, Lithuanian Energy Institute (2005) Safety Assessment and Upgrading of Maišiagala Repository (Lithuania). Upgraded Facility Safety Analysis Report. Vol. 2
  • 21.Yu C, LePoire D, Gnanapragasam E (2000) Development of probabilistic RESRAD 6.0 and RESRAD-BUILD 3.0 computer codes. NUREG/CR-6697
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BUJ7-0014-0041
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