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    Wyświetlanie 1-3 z 3
    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:
    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
    Tytuł:
    Assessment of Radiological Dose around a 3-MW TRIGA Mark-II Research Reactor
    Autorzy:
    Rahman, A. F. M. M.
    Shamsuzzaman, M.
    Rahman, M. S.
    Uddin, K.
    Yeasmin, S.
    Nazmul, Haque H. M.
    Akramuzzaman, M. M.
    Chakraborty, S. R
    Powiązania:
    https://bibliotekanauki.pl/articles/412377.pdf
    Data publikacji:
    2013
    Wydawca:
    Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
    Tematy:
    source term
    release rate
    TRIGA Mark-II reactor
    dispersion
    ingestion and deposition of radionuclide
    Gaussian plume model
    dose calculations
    Opis:
    A hypothetical accidental case of a 3-MW TRIGA Mark-II research reactor has been assumed to assess the radiological consequences due to the deposition of 137Cs and 90Sr on ground, vegetation, milk and meat. The air concentrations in sixteen cardinal directions have been estimated where the maximum concentration has been found to be at 110 m distance from the core of the reactor for all the directions. Calculated maximum doses of 137Cs, 90Sr and both 137Cs and 90Sr have been found to be within the ranges of 0.005-0.014 μSv hr–1, 0.013-0.036 μSv hr–1 and 0.018-0.05 μSv hr–1, respectively for all the directions, which are below the measured background dose limit 0.25 μSv hr–1 and also within the IAEA acceptable dose rate limit of 0.5 μSv hr–1. The calculated low doses due to the aforementioned radionuclides can be considered negligible with regard to the radiation hazards. The relationship between total effective dose rate for various pathways (i.e. immersion, inhalation, ground deposition, and ingestion of contaminated vegetation, milk, meat) and air concentration in all the directions has been established. Obtained relation reveals that the total effective dose rate is directly proportional to the air concentration, and the overall proportionality constants for 137Cs and 90Sr radionuclides have been obtained as 0.57 and 0.28, respectively. This study might provide information on the radiological safety required for the radiation protection purposes of the people living in the vicinity of the reactor site.
    Źródło:
    International Letters of Chemistry, Physics and Astronomy; 2013, 10, 2; 183-200
    2299-3843
    Pojawia się w:
    International Letters of Chemistry, Physics and Astronomy
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-3 z 3

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