Spent fuel performance data: An analysis of data relevant to the NNWSI Project

Oversby, V.M.; Shaw, Henry F.

doi:10.2172/60649

Cited by 6 publications

(2 citation statements)

References 23 publications

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“…Several studies have been performed to determine the contribution of the gap and the grain boundaries contribution to IRF [26][27][28][29][30][31][32][33][34][35][36][37]. These studies were mainly focused on caesium, strontium and technetium in UOX [26][27][28]31,32,[35][36][37], MOX [36] and CANDU [29][30][31][32][33][34] fuels. The gap contribution was obtained using cladded fuel segments meanwhile the grain boundary contribution was obtained by using powder samples.…”

Section: Introductionmentioning

confidence: 99%

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

González-Robles

Serrano‐Purroy

Sureda

et al. 2015

Journal of Nuclear Materials

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The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, and the grain boundaries and, if present, in the high burn-up structure (HBS). The values calculated from this theoretical approach correspond to an upper limit that likely does not correspond to what it will be expected to be instantaneously released in the real system. Trying to ascertain this IRF from an experimental point of view, static leaching experiments have been carried out with two commercial UO2 spent nuclear fuels (SNF): one from a pressurized water reactor (PWR), labelled PWR, with an average burn-up (BU) of 52 MWd·kgU

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Section: Introductionmentioning

confidence: 99%

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

González-Robles

Serrano‐Purroy

Sureda

et al. 2015

Journal of Nuclear Materials

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“…Spent Fuel -Leach tests with spent fuel have only been done under saturated conditions [147][148][149][150][151][152][153][154][155][156][157][158][159][160][161].…”

Section: Amentioning

confidence: 99%

Strategy for experimental validation of waste package performance assessment

Bates¹,

Abrajano²,

Wronkiewicz³

et al. 1990

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The strategy was developed by reviewing the results of laboratory analog experiments, in-situ tests, repository simulation tests, and material interaction tests.As a result of the review, a listing of dependent and independent variables that influence (1) the ingress of water inio the near-field environment, (2) the reaction between water and the waste form, and (3) the transport of radionuclides from the near-field environment was developed.The variables necessary to incorporate into an experimental validation strategy were chosen by identifying those which had the greatest effect of each of the three major events, i.e., groundwater ingress, waste package reactions, and radionuclide transport.The methodology to perform validation experiments was examined by utilizing an existing laboratory analog approach developed for unsaturated testing of glass waste forms.vii v/

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Nuclear Waste Materials

Oversby

2006

Materials Science and Technology

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Spent fuel performance data: An analysis of data relevant to the NNWSI Project

Cited by 6 publications

References 23 publications

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Strategy for experimental validation of waste package performance assessment

Nuclear Waste Materials

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