P. De Felice

National Agency for New Technologies, Energy and Sustainable Economic Development

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M. Capogni

ASL Roma

A. Fazio

National Agency for New Technologies, Energy and Sustainable Economic Development

P. Carconi

National Agency for New Technologies, Energy and Sustainable Economic Development

J D Keightley

Instituto de Radioproteção e Dosimetria

Karsten Kossert

Physikalisch-Technische Bundesanstalt

O. Nähle

Physikalisch-Technische Bundesanstalt

A. Ceccatelli

University Hospitals Birmingham NHS Foundation Trust

T. Altzitzoglou

European Commission

R. Galea

National Research Council Canada

L. Quintieri

Rutherford Appleton Laboratory

Cooperative Institutions

Istituto Nazionale di Fisica Nucleare

169

Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati

159

Commissariat à l'Énergie Atomique et aux Énergies Alternatives

134

Centre National de la Recherche Scientifique

117

National Agency for New Technologies, Energy and Sustainable Economic Development

110

Sapienza University of Rome

101

CEA Paris-Saclay

European Organization for Nuclear Research

CEA Cadarache

Istituto Nazionale di Fisica Nucleare, Sezione di Roma I

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Measurements and evaluation of the risks due to external radiation exposures and to intake of activated elements for operational staff engaged in the maintenance of medical cyclotrons

Radiation Protection Dosimetry (2009)

R. Calandrino Antonella Del Vecchio Rossella Parisi Sergio Todde P. De Felice

The aim of this paper is to assess the activation phenomena and to evaluate the risk of external exposure and intake doses for the maintenance staff of two medical cyclotrons. Two self-shielded cyclotrons are currently operating in the facility for the routine production of (11)C and (18)F. Four radiochemistry laboratories are linked to the cyclotrons by means of shielded radioisotope delivery lines. Radiopharmaceuticals are prepared both for the PET Diagnostic Department, where four CT-PET scanners are operating with a mean patient workload of 40 d(-1) and for [(18)F]FDG external distribution, to provide radiopharmaceuticals for other institutions. In spite of the fact that air contamination inside the radiochemistry laboratories during the synthesis represents the largest 'slice of the pie' in the evaluation of annual intake dose, potential contamination due to the activated particulate, generated during cyclotron irradiation by micro-corrosion of targets and other components potentially struck by the proton beam and generated neutrons, should be considered. In this regard, the most plausible long-lived (T(1/2) > 30 d) radioisotopes formed are: (97)Tc, (56)Co, (57)Co, (58)Co, (60)Co, (49)V, (55)Fe, (109)Cd, (65)Zn and (22)Na. The results for the operating personnel survey has revealed only low-level contamination for (65)Zn in one test, together with minor (18)F intake, probably due to the environmental dispersion of the radioisotope during the [(18)F]FDG synthesis.

10.1093/rpd/ncp283

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Citations (7)

Activity measurements of the radionuclide ^99mTc for the VNIIM, Russian Federation and ENEA-INMRI, Italy, in the ongoing comparison BIPM.RI(II)-K4.Tc-99m and KCRV update in the BIPM.RI(II)-K1.Tc-99m comparison

Metrologia (2016)

C Michotte M Nonis I V Alekseev I. A. Kharitonov E. E. Tereshchenko

In 2014, comparisons of activity measurements of 99m Tc using the Transfer Instrument of the International Reference System (SIRTI) took place at the VNIIM (Russian Federation) and at the ENEA-INMRI (Italy), with comparison identifier BIPM.RI(II)-K4.Tc-99m. Ampoules containing about 32 kBq of 99m Tc solutions were measured in the SIRTI for three half-lives. There are now nine results in the BIPM.RI(II)-K4.Tc-99m comparison. This comparison is linked to the BIPM.RI(II)-K1.Tc-99m comparison and the key comparison reference value (KCRV) of the BIPM.RI(II)-K1.Tc-99m has been updated to include eligible results from BIPM.RI(II)-K4.Tc-99m. The degrees of equivalence between each equivalent activity measured in the SIR or the SIRTI and the KCRV have been calculated and the results are given in the form of a table. A graphical presentation is also given. Main text To reach the main text of this paper, click on Final Report . Note that this text is that which appears in Appendix B of the BIPM key comparison database kcdb.bipm.org/ . The final report has been peer-reviewed and approved for publication by the CCRI, according to the provisions of the CIPM Mutual Recognition Arrangement (CIPM MRA).

Mutual Recognition

Standard uncertainty

10.1088/0026-1394/53/1a/06014

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Citations (1)

Supplementary comparison of the measurement of the alpha and beta particle surface emission rates from large area sources (CCRI(II)-S10 LASCE)

Metrologia (2022)

P. De Felice R Anuradha J Bludovsky Christophe Bobin R B Bosley

Main text In 2009, the Consultative Committee for Ionizing Radiation (CCRI) approved its first supplementary comparison, to be organized by the ENEA (as the pilot laboratory), for the measurement of the alpha and beta particle surface (i.e. 2 solid angle) emission rate from large area sources of the type used for calibrating surface contamination monitors. Five sources were disseminated to the twenty-three participating laboratories consisting of one each of 241Am, 14C, 147Pm and 90Sr for emission rate measurements, with one additional 90Sr source for the evaluation of source uniformity. Measurements of the radionuclide activity and radionuclidic purity were also made although not strictly required. This report describes the organization of this comparison and the material and measurement methods used. The proposed supplementary comparison reference values (SCRV) for each of the comparison measurands are given, together with the Degrees of Equivalence and their associated uncertainties for each participating laboratory. The results of this supplementary comparison may be used as evidence by participating National Metrology Institutes (NMIs) and Designated Institutes (DIs) when submitting calibration and measurement capabilities (CMCs) for the given radionuclides for similar types of large area sources; this is an important aspect of this comparison, given that only one other international supplementary comparison for surface emission rates had been organized before. To reach the main text of this paper, click on Final Report . Note that this text is that which appears in Appendix B of the BIPM key comparison database https://www.bipm.org/kcdb/ . The final report has been peer-reviewed and approved for publication by the CCRI, according to the provisions of the CIPM Mutual Recognition Arrangement (CIPM MRA).

Mutual Recognition

Alpha particle

10.1088/0026-1394/59/1a/06007

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Citations (3)

IRIDE : an interdisciplinary researchinfrastructure based on dual electron linacs&lasers : a white book

D. Alesini M. Alessandroni M. P. Anania S. Andreas M. Angelone

White paper

White (mutation)

Source

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The influence of environmental parameters in electrostatic cell radon monitor response

Applied Radiation and Isotopes (2004)

V. Roca P. De Felice A. M. Esposito Mariagabriella Pugliese C. Sabbarese

Radon Daughters

10.1016/j.apradiso.2004.03.053

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Citations (44)

Results of an international comparison for the activity measurement of 177Lu

Applied Radiation and Isotopes (2012)

Brian E. Zimmerman T. Altzitzoglou Andrei Antohe A Arinc E Bakhshandeiar

Mutual Recognition

10.1016/j.apradiso.2012.02.014

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Citations (19)

14 MeV Neutrons for 99Mo/99mTc Production: Experiments, Simulations and Perspectives

Molecules (2018)

M. Capogni A. Pietropaolo L. Quintieri M. Angelone Alessandra Boschi

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 from 99Mo/99mTc generators as pertechnetate ion, which is the ubiquitous starting material for the preparation of 99mTc radiopharmaceuticals. 99Mo in such generators is currently produced in nuclear fission reactors as a by-product of 235U fission. Here we investigated an alternative route for the production of 99Mo by irradiating a natural metallic molybdenum powder using a 14-MeV accelerator-driven neutron source.after irradiation, an efficient isolation and purification of the final 99mTc-pertechnetate was carried out by means of solvent extraction. Monte Carlo simulations allowed reliable predictions of 99Mo production rates for a newly designed 14-MeV neutron source (New Sorgentina Fusion Source).in traceable metrological conditions, a level of radionuclidic purity consistent with accepted pharmaceutical quality standards, was achieved.we showed that this source, featuring a nominal neutron emission rate of about 1015 s-1, may potentially supply an appreciable fraction of the current 99Mo 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 of 99Mo.

Nuclear fission product

10.3390/molecules23081872

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Citations (36)

Homogeneity testing of spiked reference materials

The Science of The Total Environment (1995)

R. Biagini Rainer Dersch P. De Felice S.M. Jerome E.M.E. Perkin

10.1016/0048-9697(95)04751-4

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Citations (16)

Comparison of activity concentration measurement of 63Ni and 55Fe in the framework of the EUROMET 297 project

Applied Radiation and Isotopes (1998)

P. Cassette T. Altzitzoglou R. Broda R. Collé P. Dryák

Liquid Scintillation Counting

10.1016/s0969-8043(97)10083-5

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Citations (29)

A travelling standard for radiopharmaceutical production centres in Italy

Radiation effects and defects in solids (2009)

M. Capogni P. De Felice A. Fazio

Short-lived radionuclides, γ, β+ and/or β− emitters, such as 18F, and 99mTc, particularly useful for nuclear medicine applications, both diagnostic and in radiotherapy, can be produced with high-specific activity in a small biomedical cyclotron or by a radionuclide generator. While [18F]Fludeoxyglucose ([18F]FDG) is a widely used radiopharmaceutical for positron emission tomography, the development of innovative diagnostic techniques and therapies involves the use of new radio-labelled molecules and emerging radionuclides, such as 64Cu and 124I. During the last 3 years, an extensive supply of [18F]FDG was started by many production sites in Italy, and new radiopharmaceuticals are being studied for future nuclear medical applications. Therefore, a special nuclear medicine research programme for primary standard development and transferral to the end-users has been carried out by the ENEA–INMRI. Because of the short half-lives of these nuclides, a portable well-type ionisation chamber was established as a secondary travelling standard. This device has been calibrated and transported to the radiopharmaceutical production centres in Italy where the local instrumentation, typically radionuclide calibrators, has been calibrated by a simple comparison, with an uncertainty level lower than 2%.

Nuclide

10.1080/10420150902805179

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Citations (2)