Thick solid targets for the production and online release of radioisotopes: The importance of the material characteristics – A review

Ramos, J.P.

doi:10.1016/j.nimb.2019.05.045

Cited by 27 publications

(20 citation statements)

References 80 publications

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“…ISOL target materials are typically porous, so as to facilitate radioisotope evaporation and their transport to the detecting devices. Therefore, high melting point target materials are desirable, as a high melting point typically implies the delayed material densification at high temperatures (i.e., 2000°C and above) and pore closure over time, assuring a more release-efficient operation over longer service periods [7].…”

Section: Introductionmentioning

confidence: 99%

Ta-based 413 and 211 MAX phase solid solutions with Hf and Nb

Griseri

Tunca

Huang

et al. 2020

Journal of the European Ceramic Society

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New bulk MAX phase-based ceramics were synthesized in the Ta-Hf-Al-C and Ta-Nb-Al-C systems. Specifically, (Ta1-x,Hfx)4AlC3 and (Ta1-x,Nbx)4AlC3 stoichiometries with x = 0.05, 0.1, 0.15, 0.2, 0.25 were targeted by reactive hot pressing of Ta2H, HfH2, NbH0.89, Al and C powder mixtures at 1550°C in vacuum. The produced ceramics were characterized in terms of phase composition and microstructure by X-ray diffraction, scanning electron microscopy, electron probe microanalysis and scanning transmission electron microscopy. The investigation confirmed the existence of such M-site solid solutions with low solute concentrations, as predicted by first-principles calculations. These calculations also predicted a linear trend in lattice parameter evolution with increasing Hf concentration, in agreement with the experimental results. In order to increase the low phase purity of the produced ceramics, Sn was added to form (Ta1-2 x,Hfx)4(Al0.5,Sn0.5)C3 and (Ta1-x,Nbx)4(Al0.5,Sn0.5)C3 double solid solutions, thus resulting in a higher content of the 413 MAX phase compounds in the produced ceramics.

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Section: Introductionmentioning

confidence: 99%

Ta-based 413 and 211 MAX phase solid solutions with Hf and Nb

Griseri

Tunca

Huang

et al. 2020

Journal of the European Ceramic Society

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“…After subsequent heating to 1900 • C no remaining boron was detectable during irradiation with neutrons. However, preliminary investigations show sintering at these temperatures [28], and simulations indicate possible decomposition in vacuum above 1900 • C [32]. Also taking into account the diffusion properties of boron in MgF 2 as given in ref.…”

Section: Methodsmentioning

confidence: 99%

Radioactive boron beams produced by isotope online mass separation at CERN-ISOLDE

et al. 2019

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We report on the development and characterization of the first radioactive boron beams produced by the isotope mass separation online (ISOL) technique at CERN-ISOLDE. Despite the long history of the ISOL technique which exploits thick targets, boron beams have up to now not been available. This is due to the low volatility of elemental boron and its high chemical reactivity which make the definition of an appropriate production target unit difficult. In addition, the short half-lives of all boron radioisotopes complicate tracer release studies. We report here on dedicated offline release studies by neutron capture and alpha detection done with implanted 10 B in prospective target materials, as well as molecule formation and ionization tests, which suggested the use of multiwalled carbon nanotubes (CNT) as target material and injection of sulfur hexafluoride SF 6 to promote volatile boron fluoride formation. Two target units equipped with an arc discharge electron impact ion source VADIS coupled to a water cooled transfer line to retain non-volatile elements and molecules were subsequently tested online. The measured yield of these first 8 B ISOL beams increases in the series 8 BF3 < 8 BF < 8 B < 8 BF2, reaching a maximum yield of 6.4 × 10 4 8 BF2 + ions per μC of protons.

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“…This layer should be thick enough to minimalize copious production of unwanted radionuclides in the backing plate materials. For copper targets the isotope 65 Zn, a high gamma emitter with relatively long half-life of 245 days, is produced [7]. Very often aluminum backing is preferred because of its simplicity of handling, adequate thermal properties and acceptable nuclear interactions.…”

Section: Radio-nuclidementioning

confidence: 99%

“…These properties are preferable for biocompatible Sr-(hydroxy)apatite materials for bone filling but from the point of view of their potential application as a cyclotron targets such structures are not preferable. However these material, with their relatively high surface area, may act as porous targets for the selective extraction of produced isotopes [ 65 ].…”

Section: Electrochemistry Of Targets Elementsmentioning

confidence: 99%

Potential Application of Ionic Liquids for Electrodeposition of the Material Targets for Production of Diagnostic Radioisotopes

2020

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An overview of the reported electrochemistry studies on the chemistry of the element for targets for isotope production in ionic liquids (ILs) is provided. The majority of investigations have been dedicated to two aspects of the reactive element chemistry. The first part of this review presents description of the cyclotron targets properties, especially physicochemical characterization of irradiated elements. The second part is devoted to description of the electrodeposition procedures leading to obtain elements or their alloys coatings (e.g., nickel, uranium) as the targets for cyclotron and reactor generation of the radioisotopes. This review provides an evaluation of the role ILs can have in the production of isotopes.

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Thick solid targets for the production and online release of radioisotopes: The importance of the material characteristics – A review

Cited by 27 publications

References 80 publications

Ta-based 413 and 211 MAX phase solid solutions with Hf and Nb

Ta-based 413 and 211 MAX phase solid solutions with Hf and Nb

Radioactive boron beams produced by isotope online mass separation at CERN-ISOLDE

Potential Application of Ionic Liquids for Electrodeposition of the Material Targets for Production of Diagnostic Radioisotopes

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