An electrochemical technique for fabrication of Mn-54 sources towards characterization of gamma counting nuclear instruments.

Long lived sealed radioactive sources are used for the energy calibration and efficiency determination of counting systems used in the nuclear sector. Using a sulphate bath, a facile electrochemical method was developed by electrodeposition of 54Mn on 5 mm (φ) stainless steel substrates for the preparation of 54Mn sources for such uses. Inactive sources prepared under suitable experimental parameters characterized by XRD revealed that manganese is deposited in oxide form. SEM and EDS analyses of electrodeposited surfaces confirmed uniform distribution of elements and the absence of fractures, flaws, and spatial variations. Cyclic voltammetry (CV) scans provided information about the electrochemical processes involved in the deposition process. Uniform distribution of radioactivity on surface of source was ascertained by autoradiography. Swipe tests of the encapsulated sources confirmed negligible removable surface contamination. The 54Mn sources containing up to 185KBq of 54Mn on stainless steel discs were prepared. These sources along with other longer lived sources were supplied to various users as a package of radiation sources for characterization of gamma counting systems over a wide energy range.

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.

Utilization of Chemical Deposition Technique for Preparation of Miniature 170Tm Sources and Preliminary Quality Assessment for Potential Use in Brachytherapy.

OBJECTIVE: This article describes the preparation of a 170Tm source by chemical deposition technique, its encapsulation in a titanium holder, and preliminary quality evaluation for potential utility as a brachytherapy source. METHODS: The procedure consisted of electrodeposition of Ni on a Cu wire followed by chemical deposition of 170Tm on it. Influence of feed solution pH, carrier Tm concentration, and reaction time were studied for optimum deposition of 170Tm on substrate. After sealing the source core in a titanium capsule, quality control tests were performed. Distribution of 170Tm on substrate was evaluated by autoradiography. Inactive Tm source was characterized by scanning electron microscope (SEM) and energy-dispersive X-ray (EDS) analyses. RESULTS: Under optimized conditions (pH 5, 10 µg Tm carrier, 5 h), 170Tm source core could be prepared by deposition of >95% of 170Tm radioactivity on substrate. Swipe tests and immersion tests on encapsulated sources confirmed that removable radioactivity and radioactivity leakage levels were within stipulated limits. Autoradiography of 170Tm source confirmed uniformity of radioactivity distribution. While SEM analysis confirmed good adhesion of Tm on substrate, EDS analysis confirmed elemental constituents of the Tm-deposited substrate. CONCLUSION: The objective of preparing a 170Tm source by chemical deposition for potential brachytherapy applications could be successfully achieved.

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.

A novel method for the preparation of large-area 90Sr/90Y sources for the calibration of hand contamination monitors.

This paper describes a method for the preparation of large-area (90)Sr/(90)Y polymer film sources for the calibration of hand contamination monitors. The process consists of solvent extraction of predictable quantity of (90)Sr into an organic solvent containing di-tert-butyl-cyclohexano-18-crown-6 (DCH18C6), formation of a polymeric solution of poly(methyl methacrylate) (PMMA), pouring the (90)Sr-embedded polymer solution over a surface of a defined area followed by evaporation to create a thin film and peeling-off of the radioactive PMMA film. Quality control tests of the radioactive films were carried out to ensure nonleachability, uniform distribution of activity and stability. Sources having 5kBq±428Bq were prepared using this method and routinely used for calibration of contamination monitors.

Preparation of spherical 57Co source for the calibration of intra-operative gamma probe.

This paper describes an electrochemical method for deposition of a thin layer of (57)Co on the outer surface of a copper sphere of 5mm diameter intended to be used as a point radioactive source. A description of the electrolytic cell, the process of deposition and the assay of the (57)Co activity are presented. About 1.48MBq (∼40µCi) of (57)Co could be deposited using the described method. The quality of the prepared source in terms of nonleachability, uniform distribution of activity and stability, which are necessary attributes to be ensured before application were evaluated and found to be satisfactory.

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

A novel electrochemical approach for preparation of (63)Ni sources for their application as check-light source for the calibration of thermo luminescence dosimeters (TLD) is described here. Required amount of (63)Ni on a copper substrate could be deposited by optimizing the experimental parameters such as current density, time of deposition, pH of the electrolyte and nickel ion concentration in the bath. (63)Ni sources of strength approximately 3.7 MBq could be prepared by electrodeposition at constant current on the copper matrix. Quality assurance tests to ensure nonleachability, uniform distribution of activity and stability of the sources that are necessary before application were performed.