Thickness measurement using alpha spectroscopy and SRIM

Yalçın, C.

doi:10.1088/1742-6596/590/1/012050

Cited by 5 publications

(2 citation statements)

References 16 publications

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“…x, one may take the stopping power as a constant, and above equation is turned into ∆t = ∆E/(dE/dX) E o 2019 JINST 14 P01007 Where (dE/dX) E o is the total stopping power of the material for the initial energy of the alpha particle. Using the above equation if the energy loss (∆E) measured and the total stopping power is well known, thickness of the target can be measured accurately [29]. In this measurement, Am-241 alpha source (5.486 MeV) with detector of silicon surface barrier (SSBD) was used for the measurement.…”

Section: Alpha Energy Lossmentioning

confidence: 99%

Fabrication and characterization of targets of oxidizing materials for heavy ion nuclear reaction experiments

et al. 2019

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Fabrication of targets of materials which get readily oxidized poses lot of challenges in heavy ion nuclear reaction experiments. Targets of oxidizing elements, viz. Li, Ca, Pb, Nd, Gd, Sm, Ba, Ce, Pr, Bi, Er and Eu have been frequently fabricated in target development laboratory at Inter-University Accelerator Centre (IUAC) in the form of free standing films and foils with backing support. In some cases, foils of these elements are sandwiched between two protective foils to avoid oxidation while exposed to air. Role of sandwiching (encapsulation) in minimizing the oxidation of target surface and its effect in preservation of expensive isotopic targets for longer duration is reported in the present investigations. The level of contamination from parting agents in sandwiched targets is also reported in this paper. K: Accelerator Applications; Manufacturing; Overall mechanics design (support structures and materials, vibration analysis etc); Targets (spallation source targets, radioisotope production, neutrino and muon sources) 1Corresponding author.

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Section: Alpha Energy Lossmentioning

confidence: 99%

Fabrication and characterization of targets of oxidizing materials for heavy ion nuclear reaction experiments

et al. 2019

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“…In addition, the results of this experimental production is confirmed with the TALYS code [4] and SRIM code [5] calculations as well as the available literatures. Both TALYS and SRIM codes have been widely employed in ion beam studies [6][7][8][9][10].…”

Section: Introduction mentioning

confidence: 99%

A Novel Method for 57/Ni and 57/Co Production using Cyclotron-Generated Secondary Neutrons

Suryanto

Kambali

2018

Atom Indo.

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Ni 57 Co Cyclotron Secondary neutron Nuclear medicine TALYS code 57 Ni and 57 Co radioisotpes are used in the synthesis of radiopharmaceuticals, for research purposes, as well as radiotherapy in nuclear medicine due to its decay characteristics. In this research, 57 Ni and 57 Co were produced using secondary neutrons. The secondary neutrons employed in this investigation were generated by bombarding 11 MeV protons into a target system consisting of Havar  foil as a vacuum window, aluminum foil as an energy degrader, aluminum tube as a target holder and nickel foil as a target via (p,n), (n,n) and (n,2n) nuclear reactions. The TALYS-calculated data were used to understand the origin of the secondary neutrons. In this experiment, variable Ni target thicknesses of 75, 150 and 225 m were irradiated with a fixed proton beam dose of 0.67 Ahr in order to study the dependence of the radioisotope yields on the target thickness. For the first time, 57 Ni and 57 Co radioisotopes were produced and observed experimentally following 58 Ni(n,2n) 57 Ni → 57 Co nuclear reaction. Experimental results indicated that for 225-m thick Ni target, the 57 Ni yield of 10.85 ± 3.29 Ci/Ahr and 57 Co yield of 6.04 ± 2.45Ci/Ahr were recorded after an hour cooling period. The resulted yields did not strongly depend on the target thickness. This proposed novel method is a promising method to obtain higher radioactivity yield in the production of 57 Ni and 57 Co radioisotopes.

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Simulation study of stopping power and damage profiles of H/He plasma irradiation in tungsten and its alloys for fusion power plant

Marsi

Elmaddahi

Fechtal

et al. 2022

J Radioanal Nucl Chem

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Thickness measurement using alpha spectroscopy and SRIM

Cited by 5 publications

References 16 publications

Fabrication and characterization of targets of oxidizing materials for heavy ion nuclear reaction experiments

Fabrication and characterization of targets of oxidizing materials for heavy ion nuclear reaction experiments

A Novel Method for 57/Ni and 57/Co Production using Cyclotron-Generated Secondary Neutrons

Simulation study of stopping power and damage profiles of H/He plasma irradiation in tungsten and its alloys for fusion power plant

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