Analysis of Leaching Behavior of Simulated LILW Glasses by Using the MCC-1 Test Method

KIM, Cheon-Woo; PARK, Jong-Kil; Hwang, Tae-Won

doi:10.3327/jnst.48.1108

Cited by 5 publications

(9 citation statements)

References 3 publications

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“…In addition to dissolution tests at high SA/V , monolith samples of CAB0 and CAB20 were prepared for dissolution and subsequent analysis of the altered glass surface 20 , 21 . The samples had dimensions of 70 mm × 70 mm × 2 mm and were polished to a 1-μm finish by using diamond suspension.…”

Section: Methodsmentioning

confidence: 99%

Development, characterization and dissolution behavior of calcium-aluminoborate glass wasteforms to immobilize rare-earth oxides

Kim

Corkhill

Hyatt

et al. 2018

Sci Rep

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Calcium-aluminoborate (CAB) glasses were developed to sequester new waste compositions made of several rare-earth oxides generated from the pyrochemical reprocessing of spent nuclear fuel. Several important wasteform properties such as waste loading, processability and chemical durability were evaluated. The maximum waste loading of the CAB compositions was determined to be ~56.8 wt%. Viscosity and the electrical conductivity of the CAB melt at 1300 °C were 7.817 Pa·s and 0.4603 S/cm, respectively, which satisfies the conditions for commercial cold-crucible induction melting (CCIM) process. Addition of rare-earth oxides to CAB glasses resulted in dramatic decreases in the elemental releases of B and Ca in aqueous dissolution experiments. Normalized elemental releases from product consistency standard chemical durability test were <3.62·10−5 g·m−2 for Nd, 0.009 g·m−2 for Al, 0.067 g·m−2 for B and 0.073 g·m−2 for Ca (at 90, after 7 days, for SA/V = 2000m−1); all meet European and US regulation limits. After 20 d of dissolution, a hydrated alteration layer of ~ 200-nm-thick, Ca-depleted and Nd-rich, was formed at the surface of CAB glasses with 20 mol% Nd2O3 whereas boehmite [AlO(OH)] secondary crystalline phases were formed in pure CAB glass that contained no Nd2O3.

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Section: Methodsmentioning

confidence: 99%

Development, characterization and dissolution behavior of calcium-aluminoborate glass wasteforms to immobilize rare-earth oxides

Kim

Corkhill

Hyatt

et al. 2018

Sci Rep

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“…Practically, the SPFT test is a labour-intensive process requiring many months of constant operation and the analytical analysis of leachate from a large number of samples (e.g., in excess of 1000 in the studies by Backhouse et al 71 and Fisher et al 75 . A recent assessment of SPFT data by Vienna et al 60 concluded that, when accounting for uncertainty in model parameter fitting, there was no statistically significant difference between model parameters for previously tested alkali-borosilicate glasses as long the fraction of tetrahedral boron [f( [4] B)] was greater than a threshold value of 0.22.…”

Section: Glass Durability Under Dilute Conditionsmentioning

confidence: 99%

“…Vitrification is the most common treatment technology for the immobilisation of high-level radioactive wastes (HLW) arising from spent fuel reprocessing, being applied since the late 1970's at facilities in Belgium, China, Germany, India, Japan, Pakistan, Russia, Slovakia, UK and USA (Table 1) [1][2][3] . Vitrification has also been applied to the immobilisation of lower-activity waste streams with a range of glass compositions [4][5][6] . Extensive research programmes are underway in European countries including the UK, France and Belgium, under the European H2020 research programmes, THERAMIN and PREDIS 7,8 .…”

Section: Introductionmentioning

confidence: 99%

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Forty years of durability assessment of nuclear waste glass by standard methods

et al. 2021

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Standard methods to assess the durability of vitrified radioactive waste were first developed in the 1980’s and, over the last 40 years, have evolved to yield a range of responses depending on experimental conditions and glass composition. Mechanistic understanding of glass dissolution has progressed in parallel, enhancing our interpretation of the data acquired. With the implementation of subsurface disposal for vitrified radioactive waste drawing closer, it is timely to review the available standard methodologies and reflect upon their relative advantages, limitations, and how the data obtained can be interpreted to support the post-closure safety case for radioactive waste disposal.

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“…Hal ini disebabkan berlakunya interaksi permukaan kaca dengan atmosfera (sama ada melalui bahan kimia atau fizikal) yang boleh mengubah sifat struktur kaca secara keseluruhannya. Perubahan struktur sisa kaca pegun berlaku apabila bersentuhan dengan air dan menyebabkan tindak balas, iaitu seperti berikut (Kim et al 2011;Sandgren 2019): Proses penghidratan berlaku apabila molekul air meresap masuk ke dalam struktur kaca melalui ruang bebas. Jika semakin banyak ruang bebas yang terdapat dalam struktur kaca, maka makin cepat kadar penghidratan berlaku; Proses pertukaran ion untuk membebaskan logam beralkali, yang melibatkan pertukaran hidrogen ion daripada molekul air dengan logam beralkali (M + ).…”

Section: Pembelauan Sinar-x (Xrd)unclassified

Pemegunan Bahan Radioaktif dalam Enap Cemar Minyak menggunakan Kaca sebagai Kaedah Alternatif

Ruzali¹,

Alwi²,

Idris³

et al. 2021

JSM

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Enap cemar minyak dikategorikan sebagai bahan radioaktif peringkat rendah dan pelupusan sisa ini menjadi isu penting dalam pengurusan sisa. Oleh itu, kajian ini bertujuan untuk menguruskan bahan radioaktif tabii (NORM) yang terkandung dalam sisa enap cemar minyak melalui kaedah pengacaan dan mengkaji kadar larut lesap bahan dipegun sebelum dilupuskan. Kajian mendapati bahawa sisa muatan yang optimum bagi bentuk sisa kaca adalah pada julat 20-25% bt. sisa enap cemar dan 75-80% bt. sisa kaca CRT yang dibakar pada suhu 1200°C. Ujian XRD menunjukkan kesemua bentuk sisa kaca adalah kebanyakannya amorfus dan unsur-unsur bertabur dengan sekata melalui analisis FESEM-EDX. Tambahan pula, pembebasan ternormal adalah rendah dan tidak melebihi nilai penunjuk yang dijadikan rujukan. Bentuk sisa kaca yang terhasil dalam kajian ini menunjukkan kaedah pengacaan boleh menjadi alternatif bagi pelupusan sisa enap cemar minyak yang mengandungi bahan radioaktif.

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Analysis of Leaching Behavior of Simulated LILW Glasses by Using the MCC-1 Test Method

Cited by 5 publications

References 3 publications

Development, characterization and dissolution behavior of calcium-aluminoborate glass wasteforms to immobilize rare-earth oxides

Development, characterization and dissolution behavior of calcium-aluminoborate glass wasteforms to immobilize rare-earth oxides

Forty years of durability assessment of nuclear waste glass by standard methods

Pemegunan Bahan Radioaktif dalam Enap Cemar Minyak menggunakan Kaca sebagai Kaedah Alternatif

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