Dissolution kinetics of zirconium dioxide in nitric acid

Prajapati, Ramesh R.; Srinivasan, T. G.; Chandramouli, V.; Bhagwat, Sunil S.

doi:10.1080/19443994.2013.808804

Cited by 9 publications

(5 citation statements)

References 9 publications

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“…The use of Equation ( 4) can be considered acceptable as long as the reactive surface area remains almost constant. This assumption was supported by the strong refractory character of CeO 2 and ZrO 2 [9,10], and by the associated very low dissolution rates determined in the following sections. For a congruent dissolution, the R L (i) values determined from the release in solution of each constitutive element are equal to the dissolution rate of the solid.…”

Section: Elemental Concentrations Were Determined By Icp-ms (Inductively Coupled Plasmamentioning

confidence: 70%

Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris

et al. 2020

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Nuclear fuel debris generated at the Fukushima Daiichi nuclear power plant during the loss of coolant accident in 2011, still resides within the reactor units, constantly cooled by water. Until it is retrieved, the fuel debris will corrode, releasing radioactive elements into the coolant water and the ground surrounding the reactors. To predict the corrosion behaviour of these materials, and to establish parameters for experiments with U-containing and real fuel debris, the corrosion of two surrogate fuel debris materials, with a composition of Ce(1-x)ZrxO2 (x = 0.2 and 0.4), was investigated. Materials were synthesised by a wet chemistry route and pellets were sintered at 1700°C in air atmosphere. Due to the slow corrosion kinetics, aggressive conditions were applied, and corrosion experiments were performed in 9 mol.L-1 HNO3 under static conditions. The incorporation of Zr into the structure of Ce reduced the normalised dissolution rate; from (3.75 ± 0.15) × 10-6 g.m-2.d-1 to (4.96 ± 0.28) × 10-6 g.m-2.d-1 for RL(Ce) of Ce0.8Zr0.2O2 and Ce0.6Zr0.4O2, respectively.

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Section: Elemental Concentrations Were Determined By Icp-ms (Inductively Coupled Plasmamentioning

confidence: 70%

Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris

et al. 2020

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“…In this case, it is best to adhere to using zirconium dioxide ball-milling apparatus since the resultant graphene materials would contain a lower amount of metallic impurities. This would improve the ease of purification since the common removal processes (e.g., thermal treatment at 1000 1C in a Cl 2 atmosphere, 34,47 washing with strong acids like HCl 48 and HNO 3 [49][50][51] ) could be challenging yet ineffective at times apart from the fact that the ball-milling technique also introduces structural defects to the graphene materials. Furthermore, we also underline the usage of exceedingly pure graphite as the starting material for ball-milling in this work to ensure the minimal presence of inherent metallic impurities.…”

Section: Resultsmentioning

confidence: 99%

Ball-milled sulfur-doped graphene materials contain metallic impurities originating from ball-milling apparatus: their influence on the catalytic properties

Chua

Sofer

Khezri

et al. 2016

Phys. Chem. Chem. Phys.

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Graphene materials have found applications in a wide range of devices over the past decade. In order to meet the demand for graphene materials, various synthesis methods are constantly being improved or invented. Ball-milling of graphite to obtain graphene materials is one of the many versatile methods to easily obtain bulk quantities. In this work, we show that the graphene materials produced by ball-milling are spontaneously contaminated with metallic impurities originating from the grinding bowls and balls. Ball-milled sulfur-doped graphene materials obtained from two types of ball-milling apparatus, specifically made up of stainless steel and zirconium dioxide, were investigated. Zirconium dioxide-based ball-milled sulfur-doped graphene materials contain a drastically lower amount of metallic impurities than stainless steel-based ball-milled sulfur-doped graphene materials. The presence of metallic impurities is demonstrated by their catalytic effects toward the electrochemical catalysis of hydrazine and cumene hydroperoxide. The general impression toward ball-milling of graphite as a versatile method for the bulk production of 'metal-free' graphene materials without the need for post-processing and the selection of ball-milling tools should be cautioned. These findings would have wide-reaching implications for graphene research.

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“…Perkins (1973) noted that EBWR UO2-ZrO2 fuels should be considered to contain UZr3 intermetallic, since this fuel was exposed to temperatures in excess to 350 o C. 31 Seventeen bundles of EBWR fuel contain approximately 9% UO2, 82% ZrO2, and 8% CaO core fuel. Prajapati (2014) estimates the dissolution rate for ZrO2 in nitric acid "appears to be five orders-of-magnitude" slower than for PuO2. 32 Lowalekar and Raghavan (2004) indicate that approximately 0.5 M HF solution would dissolve zirconia at a rate of 0.07 mils/hour, which might take a week and should provide sufficient fluoride to address the chemical safety concerns.…”

Section: High Zro2 Fuel Risksmentioning

confidence: 97%

“…To address vapor space concerns, sampling and characterization of various fuels, non-destructive evaluation (NDE) of all metallic-core fuels, venting of large sealed cans, removal of excess sludge, disposition of 31 Hence, these fuels would have to be treated the same as the UZr metal fuels and with a ratio of > 4 moles of fluoride per mole of zirconium, which would limit one charge per batch and require 0.5 M fluoride or greater. 32 Prajapati (2014) gives a rate in 10 M at 90 o C corresponding to a penetration rate of 1.9x10 -7 mils per hour (which is 4-5 orders of magnitude slower than PuO2). Given the pellets are 0.321" in diameter, ~160 mils penetration would be required for dissolution.…”

Section: Risk 8: H2 and Autocatalytic Reactions Due To Metal Finesmentioning

confidence: 98%

NASNF Processing and Packaging Technical Study

Reigel¹

2020

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The Accelerated Basin Deinventory (ABD) Program is designed to accelerate the deinventory of L-Basin and accelerate the SNF disposition mission. Spent fuel will be dissolved in H-Canyon with no recovery of Uranium-235 (U-235). The dissolver solutions will be temporarily stored, then transferred to the tank farms and immobilized in the Defense Waste Processing Facility. ABD accelerates basin closure, significantly reduces programmatic risk and greatly reduces the lifecycle budget requirements for the site by eliminating the need for a SNF drying and packaging project. The ABD approach represents a significant change to the clean-up approach for the Savannah River Site. The ABD Program requires changes in how H-Canyon is configured and operated. Revision viii

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Dissolution kinetics of zirconium dioxide in nitric acid

Cited by 9 publications

References 9 publications

Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris

Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris

Ball-milled sulfur-doped graphene materials contain metallic impurities originating from ball-milling apparatus: their influence on the catalytic properties

NASNF Processing and Packaging Technical Study

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