Metrofission project: An overview of the ENEA contribution

Abstract The paper describes the progress made by ENEA-INMRI in the research carried out within the framework of the Joint Research Project (JRP) ENG08 Metrofission of the European Metrology Research Programme (EMRP). This JRP aims to solve important problems related to the development of the Generation IV (GenIV) nuclear power plants in Europe as required by new demands of energy supplies that must be secure, sustainable, of high quality and also able to reduce the green house gas emissions. In the Metrofission project the ENEA-INMRI is directly involved in three Working Packages (WPs): the WP6, that aims to develop a portable Triple-to-Double-Coincidence-Ratio (TDCR) system for measuring in-situ of pure beta radionuclides; the WP7, devoted to the development of modern acquisition techniques based on Digital Coincidence Counting (DCC) with high sampling speed for radionuclide standardization; the WP8, leaded by ENEA-INMRI, which takes into account the impact of the project toward the end-users and the nuclear industry. The new prototype of the ENEA-INMRI portable TDCR counter will be presented. The preliminary results obtained in the activity measurements of 14C and 63Ni standard sources carried out by the new counter equipped with the new front-end electronics based on the CAEN Digitizer DT5720 will be discussed

Comparison of methods to determine accurate dose calibrator activity measurements

<p>Abstract</p> <p>Background</p> <p>In nuclear medicine, liquid radiopharmaceuticals for diagnostic or therapeutic purposes are administered to patients by using various types of syringes with different volumes. The activity of each "dose" must be carefully measured and documented prior to administration using an activity calibrator.</p> <p>Methods</p> <p>Calibrator response is a function of the measurement geometry and, in particular, it depends on the syringe type and filling volume. To minimize the uncertainty associated with the measured activity of the syringe, it is necessary to calculate a calibration curve depending on filling volume for each syringe type. This curve can be obtained by fitting experimentally determined volume correction factors.</p> <p>Results</p> <p>A theoretical evaluation of volume correction factors for syringes is reported for three different experimental methods. The aim is to determine the most accurate experimental method among those considered, by examining the expression of uncertainty for the correction factor. This theoretical analysis was then tested experimentally.</p> <p>Conclusion</p> <p>The agreement between the experimental data obtained in the constant activity method and gravimetric method at constant specific activity and the small associated uncertainties show the accuracy of these two procedures; while the volumetric method at constant specific activity could lead to a wrong evaluation of the correction factors.</p

14 MeV neutrons for 99Mo/99mTc production: Experiments, simulations and perspectives

Background: the gamma-emitting radionuclide Technetium-99m (99mTc) is still the workhorse of Single Photon Emission Computed Tomography (SPECT) as it is used worldwide for the diagnosis of a variety of phatological conditions.99mTc is obtained from99Mo/99mTc generators as pertechnetate ion, which is the ubiquitous starting material for the preparation of99mTc radiopharmaceuticals.99Mo in such generators is currently produced in nuclear fission reactors as a by-product of235U fission. Here we investigated an alternative route for the production of99Mo by irradiating a natural metallic molybdenum powder using a 14-MeV accelerator-driven neutron source. Methods: after irradiation, an efficient isolation and purification of the final99mTc-pertechnetate was carried out by means of solvent extraction. Monte Carlo simulations allowed reliable predictions of99Mo production rates for a newly designed 14-MeV neutron source (New Sorgentina Fusion Source). Results: in traceable metrological conditions, a level of radionuclidic purity consistent with accepted pharmaceutical quality standards, was achieved. Conclusions: we showed that this source, featuring a nominal neutron emission rate of about 1015s−1, may potentially supply an appreciable fraction of the current99Mo global demand. This study highlights that a robust and viable solution, alternative to nuclear fission reactors, can be accomplished to secure the long-term supply of99Mo

On the interaction between radon progeny and particles generated by electronic and traditional cigarettes

During their entire lives, people are exposed to the pollutants present in indoor air. Recently, Electronic Nicotine Delivery Systems, mainly known as electronic cigarettes, have been widely commercialized: they deliver particles into the lungs of the users but a “second-hand smoke” has yet to be associated to this indoor source. On the other hand, the naturally-occurring radioactive gas, i.e. radon, represents a significant risk for lung cancer, and the cumulative action of these two agents could be worse than the agents separately would. In order to deepen the interaction between radon progeny and second-hand aerosol from different types of cigarettes, a designed experimental study was carried out by generating aerosol from e-cigarette vaping as well as from second-hand traditional smoke inside a walk-in radon chamber at the National Institute of Ionizing Radiation Metrology (INMRI) of Italy. In this chamber, the radon present in air comes naturally from the floor and ambient conditions are controlled. To characterize the sidestream smoke emitted by cigarettes, condensation particle counters and scanning mobility particle sizer were used. Radon concentration in the air was measured through an Alphaguard ionization chamber, whereas the measurement of radon decay product in the air was performed with the Tracelab BWLM Plus-2S Radon daughter Monitor. It was found an increase of the Potential Alpha-Energy Concentration (PAEC) due to the radon decay products attached to aerosol for higher particle number concentrations. This varied from 7.47 ± 0.34 MeV L−1 to 12.6 ± 0.26 MeV L−1 (69%) for the e-cigarette. In the case of traditional cigarette and at the same radon concentration, the increase was from 14.1 ± 0.43 MeV L−1 to 18.6 ± 0.19 MeV L−1 (31%). The equilibrium factor increases, varying from 23.4% ± 1.11% to 29.5% ± 0.26% and from 30.9% ± 1.0% to 38.1 ± 0.88 for the e-cigarette and traditional cigarette, respectively. These growths still continue for long time after the combustion, by increasing the exposure risk

Development of a Primary Standard for Calibration of 64Cu Activity Measurement Systems

A 64Cu national primary standard was developed by the National Institute for Ionising Radiation Metrology (INMRI) of the ENEA (ENEA-INMRI) using the 4 61552 61538; Liquid Scintillation Spectrometry Method with 3H-Standard Efficiency Tracing, in literature known as CIEMAT/NIST method. The relatively short 64Cu half-life required the work to be performed at the production site. A scientific collaboration between the Institute for Health and Consumer Protection of the EC Joint Research Centre (JRC) in Ispra, where the nuclide is produced by a Scanditronix MC40 Cyclotron, and the ENEA-INMRI was then established. Significant efforts were made to identify and quantify the impurities (61Cu and 65Zn) in the mother solution. To this purpose, a new procedure for determination of pure beta emitter impurities by the CIEMAT/NIST method has been applied. A transfer standard portable well-type ionisation chamber was also calibrated, with minimum uncertainty.JRC.I.4-Nanotechnology and Molecular Imagin

Standardized Methods for Measuring Radionuclides in Drinking Water

In 2002 the Italian Standardisation Organisation (UNI)-Nuclear Energy Commission (UNICEN)- appointed a working group with the main task of writing a set of standards on drinking water measurements. To date two standards have been designed, namely, for total alpha and beta activity, and Rn-222. Further procedures are under development for measuring Ra-226 and U isotopes, and gamma-emitting radionuclides in water. The paper gives an overview of these standards, both developed and under study, with special attention to the validation of the methods.JRC.C.1-Nuclear decommissioning and facilities managemen