Site-descriptive modelling for a final repository for spent nuclear fuel in Sweden

Andersson, Johan; Skagius, Kristina; Winberg, Anders; Lindborg, Tobias; Ström, Anders

doi:10.1007/s12665-013-2226-1

Cited by 49 publications

(20 citation statements)

References 14 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In order to confirm the feasibility of a potential high level radioactive waste (HLW) repository site (Schwartz 2009;Andersson et al 2013), the retention of uranium has superior significance, provided that it is released from the conditioned waste. In Hungary, the investigation of potential host rock for HLW disposal started by studying Boda Claystone Formation (BCF).…”

Section: Introductionmentioning

confidence: 99%

Characteristics of uranium uptake of Boda Claystone Formation as the candidate host rock of high level radioactive waste repository in Hungary

et al. 2014

View full text Add to dashboard Cite

In Hungary two geological sites of the Boda Claystone Formation (BCF) located in the W-Mecsek Mountains (South Hungary) have been selected for the study of potential host rocks for high level radioactive waste (HLW), Gorica (G) Block and W-Mecsek Anticline (WMA) Block. The aim of the study was to obtain information on the uranium uptake characteristics of both sites. Our results revealed that in the sample, taken from WMA Block, where dolomites have ankerite rims and U-bearing rings, newly formed FeOOH precipitations were observed, which partly replaced the ankerite at near neutral pH (6.8). UO 2 2+ ions were adsorbed easily due to the enhanced specific surface area and high adsorption capacity of FeOOH formed from the dissolution of ankerite. The oxidation of Fe 2+ leads to the formation of FeOOH parallel to partial reduction of U 6+ to U 4+ . 75% of uranium was taken up by clay minerals and 25% by FeOOH although the ankerite concentration is as low as 6% in WMA Block of BCF. In G Block, the argillaceous matrix was found to be mainly responsible for the UO 2 2+ uptake. The study demonstrated that the U retention capacity of different BCF locations was significantly influenced by the mineralogy of these sites.

show abstract

Section: Introductionmentioning

confidence: 99%

Characteristics of uranium uptake of Boda Claystone Formation as the candidate host rock of high level radioactive waste repository in Hungary

et al. 2014

View full text Add to dashboard Cite

show abstract

“…23, issue 7). For an overview, Ström et al (2008) and Andersson et al (2013) are recommended. Below, a short summary of the Forsmark site and site investigation is given, starting with geological and mineralogical aspects and moving on to hydrogeological and hydrogeochemical aspects.…”

Section: The Sites and Previous Investigationsmentioning

confidence: 99%

“…The area is flat and lowlying and about 10 km 2 in size. Geological and geophysical downhole surveys, together with detailed mapping of the drill cores, have been conducted for 25 core drilled boreholes, with the total length of nearly 18 km (Andersson et al 2013). The boreholes have been drilled from 12 drill sites, which are displayed in Fig.…”

Section: The Sites and Previous Investigationsmentioning

confidence: 99%

Quantitative mapping and statistical evaluation of fracture minerals in the granitic bedrock at Forsmark, Sweden

Löfgren¹,

Sidborn

2016

Miner Petrol

View full text Add to dashboard Cite

This article provides quantitative data on occurrences and amounts of fracture minerals that coat discrete fractures in granitic rock at the Forsmark site in Sweden. The data are useful for retardation modelling of radionuclide and other contaminants, and for groundwater composition calculations. In a unique campaign, 2071 open fractures in groundwater conducting rock have been mapped with respect to chlorite, calcite, and pyrite. In total 767 m of drill core has been studied from very shallow rock down to~1000 m depth. The occurrences of fracture minerals, their thicknesses, and their fractions of surface coverage have been recorded for up to eight layers for each fracture. Detection limits are, for each layer, 0.1 mm for the thickness and 1 % for the surface coverage, except for pyrite crystals where surface coverages down to 0.01 % are detectable. The abundance of data has permitted statistical treatment, using parametric and non-parametric methods. Parametric fittings have been made to log-normal, truncated log-normal, and beta distributions. Chlorite, calcite, and pyrite were found in 57 %, 52 %, and 10 % of all mapped fractures, respectively. The fracture mineral thickness was 0.1 mm for calcite, 0.2 mm for chlorite, and 2 μm for pyrite, as averaged over the fracture surface area. For 50 % and 99 % of all fractures the total fracture coating thickness was less than 0.1 mm and 1 mm, respectively, which is important for diffusion resistance estimates. Average surface coverages were 18 % for calcite, 38 % for chlorite, and 0.5 % for pyrite. These data may be used for calculating the reaction capacity of flow paths.

show abstract

“…Disposal of high-level radioactive waste in deep geological layers and repositories has been widely investigated during the past decades with on-going projects in countries such as Sweden [1,2] and Belgium [3]. However, the time scale needed for the radiotoxicity of the waste to drop to the level of natural uranium is very long (i.e., of the order of 500 000 to 1 million years) [4].…”

Section: Introductionmentioning

confidence: 99%

Use of the transpiration method to study polonium evaporation from liquid lead-bismuth eutectic at high temperature

Prieto¹,

Marino²,

Lim

et al. 2014

Radiochimica Acta

View full text Add to dashboard Cite

Qualitative and quantitative understanding of Po volatilization under different conditions is of key importance for safety assessments of lead-bismuth eutectic (LBE) based nuclear reactors, spallation targets and accelerator driven systems. In this work we explore the possibilities of the transpiration method in combination with simple models to study the equilibrium and kinetics of Po evaporation from highly diluted solutions in lead-bismuth eutectic between 600 and 1000 ∘ C in Ar/5% H 2 and Ar. On the basis of evaporation experiments at various carrier gas flow rates, we identified the conditions of vapor saturation allowing the determination of equilibrium constants. From the limiting behavior at high flow rates, values for the maximal evaporation rate of Po from LBE were estimated. Measurements of evaporation as a function of time were consistent with the assumption that polonium dissolved in LBE obeys Henry's law. A theoretical analysis furthermore suggested that diffusion of polonium in LBE was not a rate limiting factor for evaporation under vapor saturation conditions. Newly determined values for the Henry constant of Po in LBE between 600 and 1000 ∘ C were consistent with previously derived correlations.

show abstract

Site-descriptive modelling for a final repository for spent nuclear fuel in Sweden

Cited by 49 publications

References 14 publications

Characteristics of uranium uptake of Boda Claystone Formation as the candidate host rock of high level radioactive waste repository in Hungary

Characteristics of uranium uptake of Boda Claystone Formation as the candidate host rock of high level radioactive waste repository in Hungary

Quantitative mapping and statistical evaluation of fracture minerals in the granitic bedrock at Forsmark, Sweden

Use of the transpiration method to study polonium evaporation from liquid lead-bismuth eutectic at high temperature

Contact Info

Product

Resources

About