Plutonium and Plutonium Compounds

Clark, David L.; Freibert, Franz J.; Jarvinen, Gordon D.

doi:10.1002/0471238961.1612212013151819.a01.pub3

Cited by 3 publications

(4 citation statements)

References 151 publications

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“…Over 2800 metric tons of plutonium (Pu) are estimated to exist worldwide, with approximately 50 metric tons added to this inventory each year as irradiated fuel from nuclear power plants. 1 Nearly 1% of this Pu inventory has been released into the environment from nuclear weapons production, weapons testing, historical waste management practices, and nuclear accidents. Significant releases have occurred worldwide, including at the Nevada National Security Site (3.1 × 10 16 Bq, 2775 kg), Savannah River Site in South Carolina (6.1 × 10 11 Bq, 0.23 kg), Los Alamos in New Mexico (3.7 × 10 11 Bq, 0.14 kg), Mayak Production Association in Russia (4.5 × 10 13 Bq, 16.9 kg), and Hanford Site located in southeastern Washington (1.85 × 10 15 Bq, 200 kg).…”

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Influences on Subsurface Plutonium and Americium Migration

Emerson

Pearce

Delegard³

et al. 2021

ACS Earth Space Chem.

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Plutonium (Pu) has been released to the environment worldwide, including approximately 1.85 × 1015 Bq (200 kg) of Pu from process waste solutions to unconfined soil structures at the Hanford Site in Washington State. The subsurface mobility of Pu is influenced by complex interactions with sediments, groundwater, and any co-contaminants within the waste stream. Previous investigations at Hanford have shown that Pu exists as discrete PuO2 particles forming before or after disposal, as secondary solid phases formed from waste interactions with sediments as adsorbed/incorporated species, and/or as dissolved species. In this research, new evidence is presented for the existence of PuO2, PuO2-Bi2O3 composites, and particles from burnt Pu metal in near-surface sediments where Pu-laden acidic process waste was disposed to sediments. Pu and americium (Am) L 3 X-ray absorption spectroscopy and density functional theory suggest that, in larger, more crystalline PuO2 particles, Am formed from radioactive decay is retained in the PuIVO2 structure as AmIV. The Pu and Am that were disposed of in an acidic waste stream have since migrated deeper into the subsurface with detection to at least 37 meters below ground surface. In contrast, Pu deposited near the ground surface from neutral pH waste is found to be homogeneously distributed and relatively immobile. Groundwater extractions performed on contaminated sediments indicate that both Pu and Am are recalcitrant, with Am being fractionally less extractable than Pu on a molar basis. These results suggest that the more mobile fraction of Am has migrated from the near-surface and may be present in the deeper sediments as a different phase than Pu. From these results, it is suggested that Pu and Am deposited from acidic wastes were initially mobile and became significantly less mobile as wastes were neutralized within the soil profile.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Influences on Subsurface Plutonium and Americium Migration

Emerson

Pearce

Delegard³

et al. 2021

ACS Earth Space Chem.

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“…Fluorite Structures. Isochronal annealing has been used by several groups to investigate structural changes in the irradiated pure oxides UO 2 , ThO 2 , CeO 2 , and PuO 2 (either using 238 PuO 2 source 167 or by self-irradiation 260 ). The stepwise nature of this process in both materials revealed the complexity of the radiation-induced defects.…”

Section: Energetics Of Radiation Damagementioning

confidence: 99%

“…Phase diagrams: U–O (adapted with permission from refs and , Copyright 2007 ASM International); Th–O (adapted with permission from refs and , Copyright 1969 Elsevier B.V.); Np–O (reprinted with permission from ref , Copyright 2016 Elsevier Ltd.) and Pu–O (adapted with permission from refs and , Copyright 2017 John Wiley & Sons, Inc. and Copyright 2009, ASM International, respectively).…”

Section: Thermodynamic Propertiesmentioning

confidence: 99%

Thermodynamics of Fluorite-Structured Oxides Relevant to Nuclear Energy: A Review

Shelyug

Navrotsky

2021

ACS Earth Space Chem.

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Fluorite structured materials have shown their applicability in various fields both on and off Earth. In particular, these oxides find extensive application in nuclear energy and the use of actinides in space and planetary settings, thermal and environmental barrier coatings, aerospace applications, catalysts, fuel cells, and batteries. Research done on thermodynamic data collection should be structured to facilitate its use in predictive calculations. In this review, we bring together several decades of experimental thermodynamic analysis of fluorite-based oxides with an emphasis on their relevance to all stages of the nuclear fuel cycle. This review is relatively short in the interest of offering an accessible perspective, especially for scientists early in their careers in nuclear science.

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Synthesis of quaternized glass fiber filter and study on its adsorption for Pu (IV)

Liu,

Wang,

Wang

et al. 2024

Emerging Materials Research

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In this study, a novel pretreatment material was developed for the separation of trace plutonium in complex systems. Glass fiber filters, known for their resistance to chemical corrosion, radiation, and thermal stability, were used as the base material for separation and enrichment. However, the number of active groups on the surface of the matrix material was limited, resulting in poor chemical grafting efficiency. To address this, a new method was proposed involving the deposition and chemical grafting. A polydopamine coating was formed on the filter’s surface through the oxidation and self-polymerization reaction of dopamine. Subsequently, the coupling agent chloromethyltrimethoxysilane and the extraction agent trioctylamine were employed to quaternize the glass fiber filter, resulting in the synthesis of a novel pretreatment material. Various characterization techniques were employed to investigate the morphology and surface functional group structure. Finally, the material was applied in the adsorption of trace plutonium and the adsorption performance and mechanism for Pu (IV) were explored. The adsorption results indicated that when the nitrate acidity was 4 mol·L−1, the adsorption capacity of the material reaches its maximum value. The adsorption capacity reached equilibrium within 360 seconds. The maximum adsorption capacity of GF-PD-CTS-TOA for Pu (IV) was 20.35 mg·g−1 (0.085 mmol·g−1). Complex anions Pu(NO3)6 2− and Pu(NO3)5 − were the main forms of Pu (IV) adsorption. This is the first time this method has been used to modify glass fiber filters and this study represents the first application of functionalized glass fiber filters in the analysis and separation of radioactive elements during reprocessing.

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Plutonium and Plutonium Compounds

Cited by 3 publications

References 151 publications

Influences on Subsurface Plutonium and Americium Migration

Influences on Subsurface Plutonium and Americium Migration

Thermodynamics of Fluorite-Structured Oxides Relevant to Nuclear Energy: A Review

Synthesis of quaternized glass fiber filter and study on its adsorption for Pu (IV)

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