MCC-1: A Standard Leach Test for Nuclear Waste Forms

Strachan, Denis M.; Turcotte, R.P.; Barnes, B.K.

doi:10.13182/nt82-a32859

Cited by 57 publications

(17 citation statements)

References 2 publications

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“…Aqueous durability was measured using two modified ASTM tests: (i) the product consistency test (PCT) 10 and (ii) the MCC-1 leach test. 11,12 Powder specimens-the surface areas of which were measured by nitrogen adsorption and the Brunauer-Emmett-Teller (BET) method-were used for the PCT test, whereas pelletized specimens-the surface areas of which were measured geometrically and via the BET method-were used for the MCC-1 test. For the PCT test, Cs 2 ZrSi 3 O 9 powders were crushed in a mortar and pestle and then placed into deionized water in a Teflon™ (DuPont, Wilmington, DE) container.…”

Section: (6) Aqueous Durabilitymentioning

confidence: 99%

Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Balmer

Bitten

et al. 2001

Journal of the American Ceramic Society

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The structure of Cs 2 ZrSi 3 O 9 synthesized using a sol-gel method was determined from the Rietveld refinement of experimental powder X-ray diffraction data. The refinement confirmed that this compound was isostructural with wadeite: its structure was hexagonal (space group P6 3 /m), and its lattice parameters were a ‫؍‬ 7.2303(2) Å and c ‫؍‬ 10.2682(4) Å. The aqueous durability of Cs 2 ZrSi 3 O 9 varied, depending on the solution conditions. In modified leach tests with buffered (pH 7) and unbuffered solutions, the 7-d cesium release rates were <1.2 ؋ 10 ؊4 g⅐(m 2 ⅐day) ؊1 , which indicated high aqueous durability. However, in unsaturated, unbuffered solutions with a pH of 9 -10, the durability was much lower, with 7-d cesium release rates of 2.2 ؋ 10 ؊3 g⅐(m 2 ⅐day) ؊1 . The ability of this material to retain cesium in aqueous environments can be explained by its condensed ring structure, in which the size of the channel openings is smaller than the diameter of a Cs ؉ ion. However, dissolution of the network silicate occurred at high pH, which resulted in the release of cesium.

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Section: (6) Aqueous Durabilitymentioning

confidence: 99%

Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Balmer

Bitten

et al. 2001

Journal of the American Ceramic Society

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“…Glass dissolution rates in deionized water were determined using procedures similar to the MCC‐1 dissolution method . Samples with final dimensions of 10 × 10 × 3 mm were polished with 800 and 1200 grit SiC paper, followed by a cerium oxide slurry to yield a mirror finish, and these were suspended by Teflon thread in 200 mL of distilled water contained in covered Teflon beakers and placed in an oven at 37°C.…”

Section: Methodsmentioning

confidence: 99%

Characterization of 20Na₂O·30((1−x)CaO·xSrO)·50P₂O₅ glasses for a resorbable optical fiber application

Freudenberger

Saitoh

Ikeda

et al. 2019

Int J of Appl Glass Sci

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Resorbable glasses with nominal molar compositions of 20Na 2 O·30[(1−x)CaO·xSrO]•50P 2 O 5 , where x = 0, 0.25, 0.50, 0.75, and 1, were prepared and characterized. With the replacement of CaO by SrO, the molar volume, refractive index, and coefficient of thermal expansion increased, and the glass transition temperature, crystallization temperature, and viscosity decreased. The replacement of CaO by SrO decreased the dissolution rate in 37°C water by nearly an order of magnitude.Resorbable glass fibers drawn from melts of the 20Na 2 O·30CaO·50P 2 O 5 glass exhibited decreasing transmission of laser light (632 nm) in a predictable way as the fiber dissolved in a phosphate buffer solution. This demonstrated that these glasses could be used to produce resorbable fibers for temporary biosensing or therapeutic applications. K E Y W O R D S

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“…The adiabatic temperature curve of the hydration reaction was recorded by an automatic temperature recorder that was dipped into the mixture while the mixture was placed into a vacuum cup. The leaching behavior of the most important nuclide, i.e., cesium, was tested according to the static immersion method of MCC-1 [29] using deionized water as the leachant and leaching at 40 ∘ C. The concentration of the Cs + in the leachant was analyzed by flame atomic absorption spectrophotometer (TAS-990). The reaction product of MPC and liquid HLW were analyzed by X-ray diffraction (XRD, Panalytical xpert Powder) with a 2 scanning rate of 0.5 ∘ /min.…”

Section: Materials and Experimentsmentioning

confidence: 99%

Effect of Fe2O3 on the Immobilization of High-Level Waste with Magnesium Potassium Phosphate Ceramic

Yang

Wu³

et al. 2019

Science and Technology of Nuclear Installations

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For the proposed novel procedure of immobilizing HLW with magnesium potassium phosphate cement (MKPC), Fe2O3 was added as a modifying agent to verify its effect on the solidification form and the immobilization of the radioactive nuclide. The results show that Fe2O3 is inert during the hydration reaction. It slows down the hydration reaction and lowers the heat release rate of the MKPC system, leading to a 3°C-5°C drop in the mixture temperature during hydration. Early comprehensive strength of Fe2O3 containing samples decreased slightly while the long-term strength remained unchanged. For the sintering process, Fe2O3 played a positive role, lowering the melting point and aiding the formation of ceramic structure. CsFe(PO4)2, or CsFePO4, was generated by sintering at 900°C. These products together with the ceramic structure and absorption benefit the immobilization of Cs+. The optimal sintering temperature for heat treatment is 900°C; it makes the solidification form a fired ceramic-like structure.

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MCC-1: A Standard Leach Test for Nuclear Waste Forms

Cited by 57 publications

References 2 publications

Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Characterization of 20Na₂O·30((1−x)CaO·xSrO)·50P₂O₅ glasses for a resorbable optical fiber application

Effect of Fe2O3 on the Immobilization of High-Level Waste with Magnesium Potassium Phosphate Ceramic

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MCC-1: A Standard Leach Test for Nuclear Waste Forms

Cited by 57 publications

References 2 publications

Synthesis, Structure Determination, and Aqueous Durability of Cs2ZrSi3O9

Synthesis, Structure Determination, and Aqueous Durability of Cs2ZrSi3O9

Characterization of 20Na2O·30((1−x)CaO·xSrO)·50P2O5 glasses for a resorbable optical fiber application

Effect of Fe2O3 on the Immobilization of High-Level Waste with Magnesium Potassium Phosphate Ceramic

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Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Synthesis, Structure Determination, and Aqueous Durability of Cs₂ZrSi₃O₉

Characterization of 20Na₂O·30((1−x)CaO·xSrO)·50P₂O₅ glasses for a resorbable optical fiber application