Uranium*

Grenthe, Ingmar; Drożdżyński, J.; Fujino, Takeo; Buck, Edgar C.; Albrecht‐Schmitt, Thomas E.; Wolf, S. F.

doi:10.1007/978-94-007-0211-0_5

Cited by 95 publications

(110 citation statements)

References 1,238 publications

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“…The linear, hexavalent actinyl ions, {O=An VI =O} 2+ , are important in solution chemistry of U [2], Np [3] and Pu [4]. The americyl ion, Am VI O 2 2+ , is a stable species in solution but is not predominant under most conditions [5].…”

Section: Introductionmentioning

confidence: 99%

Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide

Rutkowski

Ríos

Gibson

et al. 2011

J. Am. Soc. Mass Spectrom.

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Section: Introductionmentioning

confidence: 99%

Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide

Rutkowski

Ríos

Gibson

et al. 2011

J. Am. Soc. Mass Spectrom.

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“…Characterization tests showed UO 2 to be nearly stoichiometric, of nominal 6-nm diameter intrinsic particle size, and containing larger agglomerates (Sinkov et al 2008). The densities of the pure UO 2 and UO 3 ·2H 2 O phases are 10.964 g/cm 3 and 5.00 g/cm 3 , respectively (Grenthe et al 2006). …”

Section: 3mentioning

confidence: 98%

“…The beads were individually selected for roundness and size such that the 30 beads weighed 0.10 to 0.11 g in total. Based on 19.04 g/cm 3 uranium metal density (Grenthe et al 2006) for 30 beads weighing 0.1 g, the average bead diameter was about 693 μm. Three hundred uranium metal beads were used in the other two tests.…”

Section: 3mentioning

confidence: 99%

Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms

Sinkov¹,

Delegard²,

Schmidt³

2011

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Sludge formed and reposing in the K East (KE) and K West (KW) fuel storage basins on the Hanford Site has been a subject of concern since extended storage of metallic fuel from the N Reactor began in the 1980s. Although the last of the fuel was removed from the basins in 2004 and transport of sludge from the KE Basin to the KW Basin was completed in 2007, sludge still remains in the KW Basin stored in engineered containers. Sludge will be recovered from the engineered containers into Sludge Transport and Storage Containers and stored at an interim storage location on the Central Plateau. The stored sludge ultimately will be processed for disposal to the Waste Isolation Pilot Plant (WIPP) as remote-handled transuranic waste. However, before the sludge can go to WIPP, it must be processed and packaged into WIPP-acceptable forms. The presence of uranium metal fuel particles in the sludge poses problems to these operations because uranium metal reacts with water to form flammable hydrogen gas.Activities surrounding the storage, transport, treatment, and disposition of the K Basin sludge are currently administered under the Sludge Treatment Project (STP) managed by CH2M Hill Plateau Remediation Company (CHPRC) operating under contract to the U.S. Department of Energy. Investigative studies in this report were conducted by Pacific Northwest National Laboratory (PNNL) under contract to CHPRC for the STP.The reaction of uranium metal with water to form diatomic hydrogen gas (H 2 ) and uranium dioxide or uraninite (UO 2 ) proceeds by way of uranium hydride (UH 3 ). Mechanistic studies show that hydrogen radicals (H) and UH 3 serve as intermediates in the reaction of uranium metal with water to produce H 2 and UO 2 . Because H 2 is flammable, its release into the gas phase above K Basin sludge during sludge storage, processing, immobilization, shipment, and disposal is a concern to operational safety. PNNL conducted literature reviews and laboratory studies to identify methods that could be used to decrease the rate of H 2 gas generation from uranium metal corrosion in water present in sludge (Sinkov et al. 2010). Four means to decrease the H 2 evolution rate were identified for further experimental consideration:1. decreased temperature 2. reactant isolation (separation of the uranium metal from the water) 3. corrosion inhibition 4. hydrogen scavenging.The effect of decreased temperature could be inferred based on the known published rates of uranium metal reaction with water (Delegard and Schmidt 2009). Of the remaining three approaches, hydrogen scavenging appeared to be the most promising for laboratory testing, but experimental effort into reactant isolation and corrosion inhibition was also conducted and reported.Laboratory testing identified nitrate, NO 3 -, and nitrite, NO 2 -(added as their sodium salts) to be the most promising agents to minimize H 2 generation in prospective K Basin sludge operations because of their demonstrated high-attenuation factors, decreasing hydrogen generation rates hundreds-to thousan...

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“…Under these oxidizing conditions, the uranyl ion predominates and behaves as a strong acid on the Lewis acidity scale. 9 Uranyl ions show high interaction with a variety of organic and inorganic ligands to form complex species of different stabilities. 9 In systems with high dissolved carbonate concentration, uranyl-carbonate complexes may become dominant 10 and it forms soluble carbonate complexes in solution.…”

Section: Introductionmentioning

confidence: 99%

Selective adsorption of uranium (VI) on NaHCO3 leached composite γ-Methacryloxypropyltrimethoxysilane coated magnetic Ion-imprinted polymers prepared by precipitation polymerization

Tavengwa¹,

Cukrowska²,

Chimuka³

2015

S.Afr.j.chem

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Ion imprinted nano-magnetic composite polymers for selective removal of hexavalent uranium were prepared by a precipitation polymerization technique in the presence of ã-methacryloxypropyltrimethoxysilane (ã-MPS) coated magnetite and other pre-polymerization reagents. The synthesized magnetic polymers were then leached with NaHCO 3 to produce magnetic ion imprinted polymers (IIPs) with fabricated adsorption sites complementary to the uranyl ions in terms of size and shape. Several parameters were investigated to obtain conditions which gave the optimum adsorption of the uranyl onto the magnetic IIPs and their corresponding controls, magnetic ion non-imprinted polymers (NIPs). The optimum amount of magnetic sorbent, initial concentration and contact time were 50 mg, 2.5 mg L -1 and 45 min, respectively. The adsorption capacity of the magnetic IIP (1.15 ± 0.01 mg g -1 ) was higher than that of the magnetic NIP (0.93 ± 0.02 mg g -1 ). This indicated that the former had a somewhat higher affinity for U(VI) than the later. The magnetic polymers also displayed good selectivity of the order: U(VI) > Ni(II) > Mg(II). After six cycles of use, the magnetic polymers illustrated good stability and reusability.

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Uranium*

Cited by 95 publications

References 1,238 publications

Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide

Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide

Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms

Selective adsorption of uranium (VI) on NaHCO3 leached composite γ-Methacryloxypropyltrimethoxysilane coated magnetic Ion-imprinted polymers prepared by precipitation polymerization

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Uranium*

Cited by 95 publications

References 1,238 publications

Gas-Phase Coordination Complexes of UVIO22+, NpVIO22+, and PuVIO22+ with Dimethylformamide

Gas-Phase Coordination Complexes of UVIO22+, NpVIO22+, and PuVIO22+ with Dimethylformamide

Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms

Selective adsorption of uranium (VI) on NaHCO3 leached composite γ-Methacryloxypropyltrimethoxysilane coated magnetic Ion-imprinted polymers prepared by precipitation polymerization

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Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide

Gas-Phase Coordination Complexes of U^VIO₂²⁺, Np^VIO₂²⁺, and Pu^VIO₂²⁺ with Dimethylformamide