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    Wyświetlanie 1-5 z 5
    Tytuł:
    Multibarrier system preventing migration of radionuclides from radioactive waste repository
    Autorzy:
    Olszewska, W.
    Miśkiewicz, A.
    Zakrzewska-Kołtuniewicz, G.
    Lankof, L.
    Pająk, L.
    Powiązania:
    https://bibliotekanauki.pl/articles/148431.pdf
    Data publikacji:
    2015
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    engineered barrier
    migration
    radionuclides
    repository
    radioactive waste
    Opis:
    Safety of radioactive waste repositories operation is associated with a multibarrier system designed and constructed to isolate and contain the waste from the biosphere. Each of radioactive waste repositories is equipped with system of barriers, which reduces the possibility of release of radionuclides from the storage site. Safety systems may differ from each other depending on the type of repository. They consist of the natural geological barrier provided by host rocks of the repository and its surroundings, and an engineered barrier system (EBS). The EBS may itself comprise a variety of sub-systems or components, such as waste forms, canisters, buffers, backfi lls, seals and plugs. The EBS plays a major role in providing the required disposal system performance. It is assumed that the metal canisters and system of barriers adequately isolate waste from the biosphere. The evaluation of the multibarrier system is carried out after detailed tests to determine its parameters, and after analysis including mathematical modeling of migration of contaminants. To provide an assurance of safety of radioactive waste repository multibarrier system, detailed long term safety assessments are developed. Usually they comprise modeling of EBS stability, corrosion rate and radionuclide migration in near fi eld in geosphere and biosphere. The principal goal of radionuclide migration modeling is assessment of the radionuclides release paths and rate from the repository, radionuclides concentration in geosphere in time and human exposure to ionizing radiation.
    Źródło:
    Nukleonika; 2015, 60, No. 3, part 2; 557-563
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    On release of radionuclides from a near-surface radioactive waste repository to the environment
    Autorzy:
    Gudelis, A.
    Gorina, I.
    Powiązania:
    https://bibliotekanauki.pl/articles/146504.pdf
    Data publikacji:
    2015
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    near-surface repository
    radionuclides
    groundwater
    radionuclide release
    forest environment
    Opis:
    A closed near-surface radioactive waste repository is the source of various radionuclides causing the human exposure. Recent investigations confi rm an effectiveness of the engineering barriers installed in 2006 to prevent the penetration of radionuclides to the environment. The tritium activity concentration in groundwater decreased from tens of kBq/l to below hundreds of Bq/l. The monitoring and groundwater level data suggest the leaching of tritium from previously contaminated layers of unsaturated zone by rising groundwater while 210Pb may disperse as a decay product of 226Ra daughters.
    Źródło:
    Nukleonika; 2015, 60, No. 3, part 2; 551-555
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Radiation chemistry of radioactive waste to be stored in the salt mine repository
    Autorzy:
    Zagórski, Z.
    Powiązania:
    https://bibliotekanauki.pl/articles/148590.pdf
    Data publikacji:
    2006
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    dehydrogenation
    ionization spurs
    radioactive waste
    radiolysis of polymers
    repository chemistry
    Opis:
    Different aspects of radiation chemistry connected with long storage of radioactive waste are discussed. More details are given on the dehydrogenation of organic, and in particular polymeric waste, contaminated with transuranium nuclides. Determinations of radiation yields of hydrogen from typical waste were made, indicating limits of safe activities tolerable. No danger of chain reactions of hydrogen release was detected.
    Źródło:
    Nukleonika; 2006, 51,suppl.2; 87-92
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Assessment of radionuclide migration and radiological human exposure at the closed near-surface radioactive waste repository
    Autorzy:
    Gudelis, A.
    Nedveckaite, T.
    Prokopčiuk, N.
    Filistovič, V.
    Remeikis, V.
    Motiejunas, S.
    Powiązania:
    https://bibliotekanauki.pl/articles/148646.pdf
    Data publikacji:
    2010
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    near-surface repository
    engineering barriers
    radionuclide migration
    groundwater pathway
    radiation protection
    Opis:
    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.
    Źródło:
    Nukleonika; 2010, 55, 2; 251-259
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Analysis of radionuclide release through EBS of conceptual repository for Lithuanian RBMK spent nuclear fuel disposal : case of canister with initial defect
    Autorzy:
    Poskas, P.
    Narkuniene, A.
    Grigaliuniene, D.
    Kilda, R.
    Powiązania:
    https://bibliotekanauki.pl/articles/147504.pdf
    Data publikacji:
    2013
    Wydawca:
    Instytut Chemii i Techniki Jądrowej
    Tematy:
    geological repository
    near field
    radionuclide release
    radiotoxicity
    RBMK reactor
    spent nuclear fuel
    Opis:
    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.
    Źródło:
    Nukleonika; 2013, 58, 4; 487-495
    0029-5922
    1508-5791
    Pojawia się w:
    Nukleonika
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-5 z 5

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