Commercial Inconel 600 nickel-chromium alloy was implanted with nitrogen, titanium, chromium, copper with tin (as bronze components) and yttrium ions to doses ranging from 1.6e17 to 3.5e17 cm 2 . The aim of this research was to investigate the properties of the modified alloy in the context of its application in foil bearings. The virgin and the treated samples were tribologically tested and examined by Scanning Electron Microscopy, Glow Discharge Mass Spectrometry and Energy Dispersive Spectroscopy. The technological studies were preceded by modelling of concentration values of the introduced elements. The results obtained with the use of ion implantation are discussed. There are two advantages which should be highlighted: good agreement in modelling and experimental results of depth profiles of implanted ions, wear resistance improvement of Inconel 600 surface by implantation of copper and tin ions. The tribological tests indicate that abrasion and corrosion are the predominant mechanisms of surface wear.

Changes of tribological properties of Inconel 600 after ion implantation process

Radioactive contamination monitoring method and device

http://yadda.icm.edu.pl/yadda/element/bwmeta1.element.baztech-99e95ca6-b7df-4094-986b-6ead6126e839/c/pietrzak_chmielewski_powloki_1_2014.pdf.pdf

Powłoki WC-a:C i MoS 2 (Ti, W) na stopie Inconel 600 przeznaczone do pracy w łożyskach foliowych

In this research, different parameters of plastic scintillator detector were investigated by Geant4 simulation toolkit. These parameters consisted of radius, length and position of PMT as well as surface reflective type and finish options. Furthermore, response time distributions of two organic plastic materials were studied. The results indicated that collecting optical photons has a linear relationship with PMT radius head. Also, the vertical location of PMT has a non-linear relationship with the optical photons collection. However, the collection decreased by increasing PMT length or moving PMT head horizontal position. The response functions of two plastic scintillator materials were in good agreement with experimental published results. Also, Geant4 radiation transport code can simulate incident radiation photon and predict subsequent events to the PMT head very well. The results indicated that BC-404 has faster scintillation properties versus BC-400 organic scintillator materials. Comparison between Geant4 outputs illustrates that the best reflector material and surface finish type for optical photons is ground TiO2.

Geant4 Comparative Study of Affecting Different Parameters on Optical Photons Related to the Plastic Scintillation Detector

In accordance with the recommendations of the most recent Directive of Council EURATOM No. 2013/51, which concerns requirements for the protection of the health of the general public with regard to radioactive substances in water intended for human consumption, we are obligated to monitor the level of approximate dose of radioactive substances. The directive indicates two basic isotopes: tritium and radon, which ought to be monitored continuously. Essential are also para-metric values as well as frequency, methods of monitoring of radioactive substances and equipment requirements. Directive states that measurements of content of tritium and radon ought to be taken as well as calculations of approximate dose natural and artificial radionuclides content should be done, apart from tritium, potassium-40, radon and short-living products of radon disintegration. In case if one of radioactive concentrations is over 20% of computational value or concentration of tritium is over parametric value analysis of additional radionuclides is required. A detailed list of radionuclides is presented in appendix No. 3 in the Directive. Laboratory of Nuclear Control Systems and Methods in the Institute of Nuclear Chemistry and Technology (INCT) worked out a Miniature Liquid Scintillation Counter (LCS) [1] [2], within a project titled “New generation of intelligent radiometric devices with cordless transmission of information” (UDA-POIG.01.03.01-14-065/08) co-financed by European Union from the European Regional Development Fund (ERDF). This Miniature Liquid Scintillation Counter may be used as a basic equipment resulting in the above mentioned directive. This article presents results of conducted research based on LCS and comparison of this results with the measurements carried out by Accredited Laboratory for Cali-bration of Dosimetric and Radon Instruments in Central Laboratory for Radiological Protection in Warsaw (CLOR).

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Determination of Radon Content in Water Respecting to Directive of Council 2013/51/EURATOM

For measurement of hand and foot contamination with radioactive nuclides, detection probes with proportional counters are widely used. An example of such application is a whole body dosimetric stand [1] where 15 detection probes with proportional counters are used. A proportional counter shows a good detection efficiency, and practically the same sensitivity to radioactive contamination across its active measuring surface, but the counter is a costly one. Beside that, when the delicate counter window is broken for some reason, which may happen in a dosimetric stand, or the counter looses its gas tightness, the counter has to be replaced with another one, or at least repaired. Repair of the proportional counter is an expensive operation. Due to these reasons, a tendency to use plastic scintillation detectors in place of proportional counter can be observed [2–4, 7]. An advantage of a scintillation detector is a large active area of such a detector and its simultaneously high detection efficiency. A plastic scintillator in the form of a thin sheet (foil) is a convenient detector for alpha, beta, and gamma radiation and is relatively cheap. When the aluminized foil of the measuring window of a scintillation probe is mechanically damaged, it can be easily and cheaply repaired. To increase sensitivity for alpha radiation, plastic scintillators are frequently covered with a thin layer of zinc sulfide ZnS(Ag). ZnS(Ag) is deposited directly at the top of plastic scintillator, or a thin foil covered with ZnS(Ag) is added at the top of plastic scintillator. Performance of a plastic scintillator and GM pancake tubes as alpha and beta contamination detectors in dosimetric stand Bronislaw Machaj, Jan Mirowicz, Ewa Kowalska

/pdf/performance-of-a-plastic-scintillator-and-gm-pancake-tubes-1noaxixpx2.pdf

Performance of a plastic scintillator and GM pancake tubes as alpha and beta contamination detectors in dosimetric stand

Commercial Inconel 600 nickel-chromium alloy was implanted with nitrogen, chromium, titanium, yttrium and copper with tin (as bronze components) ions to doses ranging from 1.6e17 to 3.5e17 cm -2 . The main goal of the research was to investigate the properties of the modified alloy in the context of its application in foil bearings. The virgin and the treated samples were tribologically tested and examined by scanning electron microscopy (SEM) and energy dispersive spectroscopy (EDS). The technological studies were preceded by modelling of concentration values of the introduced elements. The results obtained with the use of ion implantation are discussed.

/pdf/tribological-effects-of-ion-implantation-of-inconel-600-507xsxh96u.pdf

Tribological effects of ion implantation of Inconel 600

Wireless system for radiometric measurements contains probes, for gamma radiation measurements and other probes for radon concentration measurements in air and water. The probes have the form of droplet-tight cylinders powered from a local battery. Measuring data collecting unit, based on a portable computer, communicates directly with the probes in a wireless manner using the WiFi communication network, or through the internet using mobile phone GSM network. Serial port wire connection is also possible. The local battery ensures at least 14 days of continuous operation of the probes. For long term measurements, the probes can also be powered from solar panels. Construction and operation of the probes are described. Results of scintillation probes investigation are given. Detection efficiency of the developed probes is comparable with the laboratory probes offered in our country.

Wireless system for radiometric measurements

In order to improve scintillation light collection from a thin plastic scintillator, the shape of a light reflector, and a new concept of extraction scintillation light trapped inside the scintillator were investigated. The trapped scintillation light is extracted from the scintillator by cutting the scintillator into two pieces with the edges machined at an angle of 45° and polished. Considerable improvement of detection efficiency can be achieved when the extracted and the escape scintillation light are collected together. Prototype of such a scintillation probe was constructed and investigated.

/pdf/large-area-scintillation-detector-for-dosimetric-stand-with-19unhlm5a2.pdf

Large area scintillation detector for dosimetric stand with improved light collection

LG Gamma Counter is designed for low activity measurement of the radioactive isotope iodine 125 I in liquid or solid samples during radioimmunoassay (RIA) and immunoradiometric assay (IRMA) in small or medium size clinic laboratories. Apart from RIA and IRMA programmed procedures, a measurement of small activity gamma samples is possible. The well scintillator NaI(Tl) is used as radiation detector for the isotope 125 I in the measuring channel, the well dimensions Φ being 17 × 38 mm. Gamma Counter was adapted for measuring radioactivity of single samples. The counter is equipped with an automatic system allowing transportation of examined samples to a scintillator well. The gauge is based on an integrated computer which is working under the control of Windows CE and is equipped with special software allowing for setting measurement parameters and communication with an external computer. The measured sample is placed inside the scintillator well either by an automatic sample feeder or manually. The pulses from a photomultiplier tube after amplification and shaping in pulse amplifiers are counted in the window of a single channel analyser by a programmable pulse counter under the control of microprocessor system. The measured count rate is the measure of activity of the assayed sample. Expected count rate error due to unstable operation of amplification is lower than 1%.

/pdf/laboratory-automatic-measuring-system-for-gamma-specimens-5d68tlany7.pdf

Ewa Kowalska

Papers

Performance of a plastic scintillator and GM pancake tubes as alpha and beta contamination detectors in dosimetric stand

Tribological effects of ion implantation of Inconel 600

Wireless system for radiometric measurements

Large area scintillation detector for dosimetric stand with improved light collection

Laboratory automatic measuring system for gamma specimens