Preparation of thin nuclear targets

Muggleton, A.H.F.

doi:10.1088/0022-3735/12/9/001

Cited by 32 publications

(7 citation statements)

References 159 publications

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“…While the generation of thin uranium oxide films by electrodeposition for isotopic and quantitative analysis of uranium solutions is a widely used technique [39][40][41][42], there have been few studies focusing on the composition of the generated films themselves and exact composition varies depending on experimental conditions. Maya et al [37] have reported the electroplating of thin uranium oxide films on Ni planchets.…”

Section: Characterisation Of Electroplated Uranium Oxide Filmsmentioning

confidence: 99%

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

Wilbraham

Boxall

Goddard

et al. 2015

Journal of Nuclear Materials

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h i g h l i g h t sThe first report of the presence of both UO 2 and polymeric UO 2 2+ in the same electrodeposited U oxide sample.The action of H 2 O 2 on electrodeposited U oxides is described using corrosion based concepts.Electrodeposited U oxide freely dissolves at hydrogen peroxide concentrations <100 lmol dm À3 .At [H 2 O 2 ] > 0.1 mmol dm À3 dissolution is inhibited by formation of a studtite passivation layer. At [H 2 O 2 ] P 1 mol dm À3 studtite formation competes with uranyl-peroxide complex formation. a b s t r a c tFor the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium oxide films on 316L stainless steel planchets (acting as simulant uranium-contaminated metal surfaces) has been studied. Analysis of the H 2 O 2 -mediated film dissolution processes via open circuit potentiometry, alpha counting and SEM/EDX imaging has shown that in near-neutral solutions of pH 6.1 and at [H 2 O 2 ] 6 100 lmol dm À3 the electrodeposited uranium oxide layer is freely dissolving, the associated rate of film dissolution being significantly increased over leaching of similar films in pH 6.1 peroxide-free water. At H 2 O 2 concentrations between 1 mmol dm À3 and 0.1 mol dm À3 , formation of an insoluble studtite product layer occurs at the surface of the uranium oxide film. In analogy to corrosion processes on common metal substrates such as steel, the studtite layer effectively passivates the underlying uranium oxide layer against subsequent dissolution. Finally, at [H 2 O 2 ] > 0.1 mol dm À3 the uranium oxide film, again in analogy to common corrosion processes, behaves as if in a transpassive state and begins to dissolve. This transition from passive to transpassive behaviour in the effect of peroxide concentration on UO 2 films has not hitherto been observed or explored, either in terms of corrosion processes or otherwise. Through consideration of thermodynamic solubility product and complex formation constant data, we attribute the transition to the formation of soluble uranyl-peroxide complexes under mildly alkaline, high [H 2 O 2 ] conditions -a conclusion that has implications for the design of both acid minimal, metal ion oxidant-free decontamination strategies with low secondary waste arisings, and single step processes for spent nuclear fuel dissolution such as the Carbonate-based Oxidative Leaching (COL) process.

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Section: Characterisation Of Electroplated Uranium Oxide Filmsmentioning

confidence: 99%

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

Wilbraham

Boxall

Goddard

et al. 2015

Journal of Nuclear Materials

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“…Increasing the amount of water made Pb react with it and decreasing did not result in floating successfully. After floating the targets films were fished onto target frames of standard size [15]. In order to remove the water from the area corresponding to the desired film, it was rapidly flushed out using isopropyl alcohol poured drop-by-drop using a syringe.…”

Section: Floating Of Lead Filmsmentioning

confidence: 99%

Fabrication of self-supporting targets of lead ( 206,208 Pb) using evaporation technique

Goyal¹,

Abhilash²,

Kabiraj³

et al. 2015

Nuclear Instruments and Methods in Physics Research Section A:

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“…The targets were preparated by physical vapour deposition [8,9] at high vacuum conditions using zinc wires provided by GoodFellow with a 99.95% of purity. Using an evaporation facility implemented recently in the laboratory, the zinc wires were evaporated over microscope glass coated with layer of BaCl 2 .…”

Section: Target Preparationmentioning

confidence: 99%

Production yields of^NatZn(p,x)⁶⁷Ga reaction in the energy range of 1.6 to 2.5 MeV

Wächter

Miranda

Cancino

et al. 2008

J. Phys.: Conf. Ser.

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Preparation of thin nuclear targets

Cited by 32 publications

References 159 publications

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

Fabrication of self-supporting targets of lead ( 206,208 Pb) using evaporation technique

Production yields of^NatZn(p,x)⁶⁷Ga reaction in the energy range of 1.6 to 2.5 MeV

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Preparation of thin nuclear targets

Cited by 32 publications

References 159 publications

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

Fabrication of self-supporting targets of lead ( 206,208 Pb) using evaporation technique

Production yields ofNatZn(p,x)67Ga reaction in the energy range of 1.6 to 2.5 MeV

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Production yields of^NatZn(p,x)⁶⁷Ga reaction in the energy range of 1.6 to 2.5 MeV