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  • The influence of source term model parameters on the release rates of critical radionuclides from the near-field region of the final disposal of the spent fuel was studied by numerical experiments. It was stated that the extent of their influence depends also on the type of the studied nuclide. The migration of the solubility-limited nuclides is influenced by physical parameters of the system more significantly than that of other nuclides. It could be also recommended to bind the modelled leaching of all nuclides with the degradation of fuel matrix controlled preferentially by leaching of uranium that depends on its solubility limitation and retardation in the bentonite backfill.
  • The influence of source term model parameters on the release rates of critical radionuclides from the near-field region of the final disposal of the spent fuel was studied by numerical experiments. It was stated that the extent of their influence depends also on the type of the studied nuclide. The migration of the solubility-limited nuclides is influenced by physical parameters of the system more significantly than that of other nuclides. It could be also recommended to bind the modelled leaching of all nuclides with the degradation of fuel matrix controlled preferentially by leaching of uranium that depends on its solubility limitation and retardation in the bentonite backfill. (en)
  • Vliv parametrů zdrojového členu na rychlosti uvolňování kritických radionuklidů z oblasti pole blízkých interakcí trvalého úložičtě vyhořelého jaderného paliva byl sledován numerickými experimenty. Bylo zjištěno, že rozsah jejich vlivu záleží také na typu studovaných nuklidů. Migrace nuklidů, jejichž rozpouštění je koncentračně limitováno, je ovlivňována změnou fyzikálních parametrů více než migrace ostatních nuklidů. Můžeme dále doporučit svázat uvolňování radionuklidů z matrice paliva s modelovaným loužení uranu, které je omezováno jednak mezí rozpustnosti uranu, jednak retardací jeho migrace ve vrstvě tlumícího bentonitu. (cs)
Title
  • Importance of the Source Term Description in the Safety Assessment of Spent Fuel Disposal
  • Význam popisu zdrojového členu v bezpečnostních studiích úložiště vyhořelého jaderného paliva (cs)
  • Importance of the Source Term Description in the Safety Assessment of Spent Fuel Disposal (en)
skos:prefLabel
  • Importance of the Source Term Description in the Safety Assessment of Spent Fuel Disposal
  • Význam popisu zdrojového členu v bezpečnostních studiích úložiště vyhořelého jaderného paliva (cs)
  • Importance of the Source Term Description in the Safety Assessment of Spent Fuel Disposal (en)
skos:notation
  • RIV/68407700:21340/05:04115382!RIV06-MSM-21340___
http://linked.open.../vavai/riv/strany
  • 686 ; 687
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  • P(1H-PK/25), Z(MSM 210000020)
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  • 524394
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  • RIV/68407700:21340/05:04115382
http://linked.open...riv/jazykVysledku
http://linked.open.../riv/klicovaSlova
  • final disposal; performance assessment; source term; spent fuel (en)
http://linked.open.../riv/klicoveSlovo
http://linked.open...ontrolniKodProRIV
  • [35497EFCE7FE]
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  • Praha
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  • Prague
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  • CTU Reports - Proceedings of Workshop 2005
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http://linked.open...vavai/riv/projekt
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  • Vopálka, Dušan
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number of pages
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  • České vysoké učení technické v Praze
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  • 80-01-03201-9
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  • 21340
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