An electrochemical method for the preparation of 63Ni source for the calibration of thermoluminescence dosimeter (TLD)

Fabrication of miniature 141Ce sources by chemical deposition towards possible use in the performance evaluation of gamma cameras - A feasibility study

¹⁴¹Ce sources were fabricated for quality assurance of gamma cameras. The fabrication process consisted of electro-deposition of Ni on a Cu sphere in 0.01 N H₂SO₄ containing 30 mg/mL H₃BO₃ and 50 μg of NiSO₄·7H₂O at pH 2-3 followed by deposition of ¹⁴¹Ce on it. > 95% deposition of ¹⁴¹Ce on substrate could be achieved at pH 5. Source core was loaded in custom-made Al holder. Autoradiography confirmed uniform activity distribution. SEM and EDS analyses confirmed deposition of Cerium on substrate.

A chemical deposition method to prepare circular planar 147Pm sources for the measurement of particulate emission in air

This paper describes a method for preparing a circular planar source of 17 mm diameter containing approximately 400 kBq of (147)Pm employing a wet chemical deposition technique to be used in dust monitors. This manuscript described the overall process concept and experimental procedure. The technical feasibility, efficiency of the process and product quality has been evaluated. The quality of the prepared source in terms of nonleachability, uniform distribution of activity and stability, which are necessary attributes of a radioactive source were evaluated and found to be satisfactory.

Preparation of 57Co point sources for the performance evaluation of nuclear imaging instruments

This paper describes the utility of electrodeposition method to prepare (57)Co point sources. A description of the electrolytic cell, the process of (57)Co electrodeposition, encapsulation and quality control of the sealed (57)Co sources is presented. Sources containing ~3.7-4.81 MBq (0.10-0.13 mCi) of (57)Co were prepared, encapsulated in miniature titanium capsules and subjected to quality control tests to ensure compliance with regulatory requirements. The encapsulated (57)Co sources prepared by the reported procedure were found to be effective in routine performance evaluation of nuclear medicine instruments.

An electrochemical route to prepare planar 204Tl sources for the calibration of beta surface contamination monitors

This paper describes the utility of the electrochemical technique for the preparation of a circular planar 204Tl source required for the calibration of beta surface contamination monitors. The electrolytic cell, the experimental set up used and the process of deposition are described. The factors that influence the electrodeposition of 204Tl onto the circular copper substrate were investigated and a careful control has been exercised to ensure an optimum deposition of the 204Tl activity onto the substrate. The morphology of the deposited layer was examined by SEM, AFM and EDS analyses. Sources containing ∼3.7 MBq (∼0.1 mCi) 204Tl on a copper sheet of 20 mm diameter working area were prepared and housed in a holder. Quality control tests on the leachability, distribution of activity and stability of the source were performed to ensure compliance with regulatory safety requirements.

A novel and facile approach for the preparation of 133Ba source core, encapsulation and quality evaluation

This paper describes a facile and effective method to prepare 133Ba source exploiting the intrinsic properties of the anodized titanium to electro-deposit 133Ba from an aqueous solution. The process consists of anodization of Ti rod [4.8 mm (∅)  ×  10 mm (l)] to create a reactive surface to permit cathodic electrodeposition of 133Ba from an aqueous solution. The factors that influence the electrodeposition of 133Ba onto the anodized titanium substrate were identified and a careful control has been exercised to ensure optimum deposition of 133Ba activity onto the substrate. The morphology of the electrodeposited samples were examined by SEM and EDS analyses. Sources containing ∼ 3.7–11.1 MBq (0.1–0.3 mCi) 133Ba were prepared, encapsulated successfully in titanium capsules and subjected to quality control tests to ensure compliance with mandatory regulatory safety requirements.

An electrochemical technique to prepare 55Fe source for the calibration of the X-ray detectors

This paper describes an electrochemical method for the preparation of 55Fe sources, utilized in the calibration of low energy X-ray detectors. In this process, electrodeposition of 55Fe containing 185 MBq (∼5 mCi) of activity on a small circular cross sectional flat surface area (∼0.07 cm2) within a cylindrical Cu metal rod was carried out at a current density of 20 mA/cm2 at 18 ºC for 4 h using sulphate bath maintained at pH ∼ 2. The electrolytic cell, the experimental set up used and the process of 55Fe deposition were described. The effect of various experimental parameters influencing the electrodeposition of 55Fe were identified and optimized. The texture and morphology of the electrodeposited samples were examined by X-ray diffraction (XRD), SEM and EDS techniques. The quantity of deposited 55Fe activity was assayed in a calibrated ion chamber. Quality control tests were carried out to ensure nonleachability, uniform distribution of activity and stability of the sources.

Development of a 125I source for its application in bone densitometry

This paper describes a method for the preparation of (125)I sources for their use in bone densitometer. The process consists of preparation of silver pellets of size ∼2.5 mm (ϕ) × 0.6 mm (l) by 'Cold die compaction technique', palladium coating of the silver pellets, adsorption of (125)I on the palladium coated silver pellets and encapsulation source matrix in a titanium capsule [ 3 mm (ϕ) × 10 mm(l)] using Nd:YAG laser. The texture and morphology of the source matrix were examined by SEM and EDS analyses. Encapsulated sources containing (125)I activity up to ∼1.85 GBq (50 mCi) were prepared. Quality control tests that were necessary before application were performed and gave satisfactory results.

Development of a micro electrochemical cell for in-situ deposition of 63Ni for use in electron capture detector (ECD) in gas chromatography

In this work, we describe a novel electrochemical approach to deposit 63Ni coatings on the inner surface of a copper annular ring for its application as an ionization source in electron capture detector of gas chromatograph. A description of the electrolytic cell, the process of deposition and the experimental set up used, analysis of the nickel deposit and results are presented in this article. Sources containing ∼370 MBq (∼10 mCi) 63Ni could be prepared. The quality of the prepared source in terms of nonleachability, uniform distribution of activity and stability that are necessary before application were evaluated and found to be highly satisfactory.

On the application of electrochemical techniques for the preparation of 57Co source core, encapsulation and quality evaluation for radiometric assay of nuclear fuel rods

This paper describes an electrochemical method for the preparation of 57Co source to be used in quality evaluation of nuclear fuel rods. The electrolytic cell, the experimental set up used and the process of deposition are described. The effect of various parameters such as pH of the electrolyte, bath temperature, current density, content of cobalt in the bath, electrolyte volume in the cell and deposition time were investigated and optimized for maximum deposition. The texture and morphology of the electrodeposited samples were examined by X-ray diffraction (XRD), SEM and EDS analyses. Sources containing ∼370 MBq (10 mCi) 57Co on a circular copper foil of 4 mm diameter could be prepared and encapsulated in an aluminum capsule. Quality assurance tests performed to ensure non-leachability, uniform distribution of activity and stability of the sources gave satisfactory results.

Development of a (147)Pm source for beta-backscatter thickness gauge applications

This paper describes a method for the preparation of (147)Pm sources, utilized in the determination of graphite coating thickness on the inner surface of the zircaloy cladding tube of nuclear fuels. (147)Pm was adsorbed on a limited surface area [1.5mm (ϕ)×2mm (l)] of a cylindrical aluminum rod [1.5mm (ϕ)×10mm (l)]. In brief, the selected tip area [1.5mm (ϕ)×2mm (l)] was anodized at a current density of 15mA/cm(2) at 15°C in 3M·H(2)SO(4) for 2h followed by immersion of this area in 10μL of (147)Pm solution containing 37MBq (1mCi) of activity at pH 6.0 for 24h. The radioactive area was subsequently covered with a thin layer of Polymethyl Methacrylate (PMMA) to prevent leaching of (147)Pm from the source. The quantity of incorporated (147)Pm activity was assayed in a calibrated ion chamber. Quality control tests were carried out to ensure nonleachability, uniform distribution of activity and stability of the sources.