Radionuclide Migration through Sediment and Concrete: 16 Years of Investigations

Golovich, Elizabeth C.; Mattigod, Shas V.; Snyder, Michelle M.V.; Powers, Laura; Whyatt, Greg A.; Wellman, Dawn M.

doi:10.2172/1167312

Cited by 7 publications

(8 citation statements)

References 92 publications

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“…Langton (2014) suggests that Cr and Tc reoxidation occurs faster in monoliths buried in 4.14 Hanford sediment kept under unsaturated conditions than monoliths held in water saturated conditions. On the other hand, studies reviewed in Golovich et al (2014) suggest that the effective diffusion coefficient (D e ) for contaminants such as Tc(VII) and iodide leaching from spiked concrete into unsaturated Hanford sediments are several orders of magnitude lower than D e values for the same COCs present in other cementitious waste forms that are leached in the traditional water saturated conditions. In a similar fashion, Golovich et al (2014) reviewed studies where COCs were spiked into Hanford sediments that were contacted with uncontaminated Hanford sediments in half-cell diffusion tests.…”

Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

“…On the other hand, studies reviewed in Golovich et al (2014) suggest that the effective diffusion coefficient (D e ) for contaminants such as Tc(VII) and iodide leaching from spiked concrete into unsaturated Hanford sediments are several orders of magnitude lower than D e values for the same COCs present in other cementitious waste forms that are leached in the traditional water saturated conditions. In a similar fashion, Golovich et al (2014) reviewed studies where COCs were spiked into Hanford sediments that were contacted with uncontaminated Hanford sediments in half-cell diffusion tests. In these tests, the diffusion of the COCs from the spiked sediment cell into the uncontaminated sediments was systematically lower as the moisture content in the two sediment filled cells was reduced from saturated conditions down to 7 wt% and then 4 wt%.…”

Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

“…Besides the classical half-cell diffusion cell technique described in Golovich et al (2014) and the primary references cited within, one methodology/instrumentation that allows controlled unsaturated conditions to be maintained is the pressurized unsaturated flow (PUF) system (see Westsik et al 2013b Figure 4.8 and Section 4.10.5 for more details). PUF tests on Cast Stone/ETF-processed grouts can use either intact monoliths or disaggregated material.…”

Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

See 2 more Smart Citations

Extended Leach Testing of Simulated LAW Cast Stone Monoliths

Serne

Westsik

Williams

et al. 2015

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The term effective diffusion coefficient used in this report is called observed diffusion coefficient in EPA Method 1315 documents. ANSI/ANS16.1 uses the symbol D with no subscript and names D =effective diffusion coefficient. ASTM C1308 method uses the symbol D e and name effective diffusion coefficient. In some literature this parameter, the D e value in Equations 1 and 4 is called apparent diffusion coefficient, D a (see for example Grathwohl (1998). All three names are equivalent and are "quantified" in standard leach tests by Equations 2 and 4. De σ De σ 7d to 604/609 d 28 d to 63 d 28 d to 604/609 Avg. Avg. Avg. Monolith Tc(VII)

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Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

Section: Potential Methodologies/experiments To Measure Coc Release Fmentioning

confidence: 99%

See 1 more Smart Citation

Extended Leach Testing of Simulated LAW Cast Stone Monoliths

Serne

Westsik

Williams

et al. 2015

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“…respectively. Golovich et al (2014) describe analysis of half-cell data using a statistical "probit" function that is related to the normal distribution and inverse error function:…”

Section: Half-cell Leachingmentioning

confidence: 99%

Solid Secondary Waste Data Package Supporting Hanford Integrated Disposal Facility Performance Assessment

Flach¹,

Kaplan²,

Nichols³

et al. 2016

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This data package provides recommendations for waste form physical and chemical properties to support the initial analysis of Solid Secondary Waste (SSW) disposals in the 2017 Integrated Disposal Facility (IDF) Performance Assessment (PA). At this time, specific formulations have not been identified for cementitious materials that will be used to encapsulate or solidify SSW, and no IDF-specific experiments were conducted to obtain data for the PA. Thus recommended property values are provided for a range of candidate materials, and based on a review of existing literature. Four key SSW streams were identified for emphasis due to expected inventories for contaminants of potential concern (COPC): HEPA filters, ion exchange resins, carbon adsorber beds and Ag-mordenite. Based on current disposal plans, compacted HEPA filters were considered as an encapsulated waste form and the other three key waste streams were assumed to be blended and solidified in a cementitious matrix. Considerations for alternative disposal methods were also addressed. The IDF PA team identified specific COPCs expected to be the key contributors for the PA calculations: Tc-99, I-129, Cs-137, Sr-90, uranium isotopes (and total uranium), chromium, mercury and nitrate. These species are the focus of this data package.

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“…Some of these models are empirical (JSCE 2010;Andrade et al 2013), while others incorporate sophisticated theory. However, there are few studies that analyse the contamination in real structures; thus, the existing studies may not help estimate the contamination at F1NPS (Farfan et al 2011;Golovich et al 2014;Yamada et al 2019). Therefore, the contamination estimations should be performed using a theoretical approach.…”

Section: Framework Of the Research Projectmentioning

confidence: 99%

General Overview of the Research Project Investigating the Radionuclide Solution Behavior in Mock Mortar Matrix Modeled after Conditions at the Fukushima-Daiichi Nuclear Power Station

Igarashi

Haga²,

Yamada

et al. 2021

ACT

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Decommissioning of the Fukushima Daiichi Nuclear Power Station (F1NPS) in a proper manner requires assessment of the contamination levels and mechanisms for contamination in the concrete structures. Between January 2018 and March 2020, Japan's Ministry of Education Ministry of Education, Culture, Sports, Science and Technology (MEXT) conducted a project called "The Analysis of Radionuclide Contamination Mechanisms of Concrete and the Estimation of Contamination Distribution at the Fukushima Daiichi Nuclear Power Station". In this review, we outline the results of this study. The experimental results from the first project indicate that concrete carbonation, Ca leaching, and drying conditions affected the adsorption behaviors of Cs and Sr and therefore, their penetration depths. Additionally, the studies showed that α-nuclides precipitated on the surface of the samples because concrete causes a high pH. A reaction transport model was developed to assess further the adsorption characteristics of Cs and Sr in carbonated cement paste and on concrete aggregates. The model used real concrete characteristics from the materials used at F1NPS and historical boundary conditions at the site, including radionuclide concentrations and penetration profiles within the turbine pit wall. Capillary water suction resulting from dried concrete was evaluated by considering structural changes in cement hydrates using X-ray CR and 1 H-NMR relaxometry.

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Radionuclide Migration through Sediment and Concrete: 16 Years of Investigations

Cited by 7 publications

References 92 publications

Extended Leach Testing of Simulated LAW Cast Stone Monoliths

Extended Leach Testing of Simulated LAW Cast Stone Monoliths

Solid Secondary Waste Data Package Supporting Hanford Integrated Disposal Facility Performance Assessment

General Overview of the Research Project Investigating the Radionuclide Solution Behavior in Mock Mortar Matrix Modeled after Conditions at the Fukushima-Daiichi Nuclear Power Station

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