Performance of a buried radioactive high level waste (HLW) glass after 24 years

Jantzen, Carol M.; Kaplan, Daniel I.; Bibler, N.E.; Peeler, David K.; Plodinec, Milivoj

doi:10.1016/j.jnucmat.2008.06.040

Cited by 63 publications

(35 citation statements)

References 47 publications

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“…Field testing procedure used was typical for long-term field tests carried out to analyse the performance of wasteforms [13,18,[26][27][28]. The water which contacted cementitious wasteforms was periodically collected and analysed.…”

Section: Test Procedures For Radioactive Componentsmentioning

confidence: 99%

Long-term field and laboratory leaching tests of cemented radioactive wastes

Ojovan

Varlackova²,

Golubeva³

et al. 2011

Journal of Hazardous Materials

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Experiments with real and simulated radioactive cementitious wasteforms were set up to compare the leaching behaviour of cementitious wasteforms containing nuclear power plant operational waste in field and laboratory test conditions. Experiments revealed that the average annual 137 Cs leach rate in deionised water was about thirty-five times greater compared with the measured average value for the 1 st year of the field test. Cumulative leached fraction of 137 Cs for 1 st year (3.74%) was close to values reported in literature for similar laboratory experiments in deionized water, however more than two orders of magnitude higher than the 1 st year leached fraction of 137 Cs in the repository test (0.01%). Therefore, to compare field and laboratory test results, a scaling factor is required in order to account for surface to volume factor difference, multiplied by a temperature factor and a leach rate decrease coefficient related to the ground water composition.

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Section: Test Procedures For Radioactive Componentsmentioning

confidence: 99%

Long-term field and laboratory leaching tests of cemented radioactive wastes

Ojovan

Varlackova²,

Golubeva³

et al. 2011

Journal of Hazardous Materials

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“…Depending on the type of alteration phase, the glass-water reaction can increase from the residual rate and return to the forward rate (e.g., Stage IV -alteration rate renewal). This type of behavior has been observed in accelerated weathering experiments and may be associated with the Al:Fe ratio of the glass formulation (Jantzen et al, 2008).…”

Section: Short and Long-term Corrosion Ratesmentioning

confidence: 58%

Mathematical Formulation Requirements and Specifications for the Process Models

Steefel¹,

Moulton²,

Pau³

et al. 2010

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“…Such minerals perhaps are the key factor which would determine the glass dissolution remaining in "residual rate" regime or "resumption of alteration" regime. During glass alteration, the formation of clay mineral assemblages on the leached glass surface layers caused the dissolution rate to remain in a long term residual rate, but the formation of zeolite mineral assemblages on the leached glass surface layers caused the dissolution rate to increase and return to the initial high forward rate [27,76]. But the formation mechanisms and conditions are not fully studied.…”

Section: Recommendationsmentioning

confidence: 99%

A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

Jivkov

et al. 2017

Journal of Nuclear Materials

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Abstract:Understanding the alteration of nuclear waste glass in geological repository conditions is critical element of the analysis of repository retention function. Experimental observations of glass alterations provide a general agreement on the following regimes: inter-diffusion, hydrolysis process, rate drop, residual rate and, under very particular conditions, resumption of alteration. Of these, the mechanisms controlling the rate drop and the residual rate remain a subject of dispute. This paper offers a critical review of the two most competitive models related to these regimes: affinity-limited dissolution and diffusion barrier. The limitations of these models are highlighted by comparison of their predictions with available experimental evidence. Based on the comprehensive discussion of the existing models, a new mechanistic model is proposed as a combination of the chemical affinity and diffusion barrier concepts. It is demonstrated how the model can explain experimental phenomena and data, for which the existing models are shown to be not fully adequate.Key words: nuclear waste glasses, long-term dissolution, mechanisms, modelling IntroductionRadioactivity wastes are generated at all stages of the nuclear fuel cycle, including the decommissioning of nuclear facilities, as well as from military applications. Of particular concern for the storage/disposal of radioactivity wastes are those containing long-lived radionuclides [1].The current plan ( countries such as Belgium, Finland , Sweden , France etc.)for long-term management of such wastes is to store them in deep, stable and lowpermeable geological formations [2].The storage design is based on the so-called multi-barrier concept, where several barriers prevent for a period of time, or slow down the release and migration of radionuclides through the geosphere [3,4].Within this concept, hazardous nuclides are immobilized into solidified bodies. The wasteform selection is difficult, since durability is not the sole criterion [5]. Currently, vitrification is regarded as the best solution for immobilizing radionuclides. This technology has been progressively developed over the last half-century, has matured and has become industrially robust.Data collected to date suggest that glass waste forms offer the advantages that they can accommodate a wide range of waste streams, are resistant to radiation damage, and are relatively inert to both chemical and thermal perturbations [6].The use of natural and archeological analogues supported further the durability argument of glass as waste forms [7][8][9][10][11]. Except for the alumino-phosphate glass used in Russia, the borosilicate glass has been universally selected by all other nations [12].In order to make scientifically-underpinned safety cases, the long-term behaviour of glassy wasteforms requires further understanding and assessment. Half-lives of some radionuclides extend to millions of years, requiring isolation for geological periods, while the period of investigation possible in the field and the la...

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Performance of a buried radioactive high level waste (HLW) glass after 24 years

Cited by 63 publications

References 47 publications

Long-term field and laboratory leaching tests of cemented radioactive wastes

Long-term field and laboratory leaching tests of cemented radioactive wastes

Mathematical Formulation Requirements and Specifications for the Process Models

A mechanistic model for long-term nuclear waste glass dissolution integrating chemical affinity and interfacial diffusion barrier

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