Towards a More Inclusive Future: A Comprehensive Assessment of Gender Diversity in Nuclear Medicine Education, Training and Workforce.

The field of nuclear medicine has undergone remarkable advances, particularly with the introduction of new devices, radionuclides for imaging and therapy, new clinical applications, and emergence of medical evidence. As this dynamic field continues its rapid expansion, there is an urgent need to increase the number of well-trained professionals globally. Consequently, advocating for nuclear medicine as a thriving field of study and work for women becomes paramount in ensuring the establishment of a robust workforce capable of meeting the growing demands. True gender equality will only be achieved when there is equal representation across the spectrum of the nuclear medicine professions, including nuclear medicine technologists, radiopharmacists, radiochemist, medical physicists, nuclear medicine physicians, administrators, academics, and leaders. Currently, the workforce exhibits an imbalance, with females predominating among nuclear medicine technologists, while the number of female physicians, and those in leadership positions remains comparatively lower. There are various factors which contribute to the existing inequities. Societal expectations often impose traditional gender roles that somehow discourage women from pursuing a career in the science, technology, and mathematics (STEM) fields, including nuclear medicine. Additionally, prevailing unequal work conditions and gender biases within the workplace can create barriers that hinder women's professional growth and development. Ways of addressing inequalities includes ensuring female participation at all levels of education and training and promoting the field at undergraduate level in medical school. Mentorship programs have demonstrated great success in guiding and supporting women at various stages of their careers. Therefore, there is a need for their expansion and enhancement. Furthermore, female role models play a pivotal role in shattering gender stereotypes and inspiring other women to pursue careers in nuclear medicine and its related fields. By addressing the existing imbalances and fostering an environment that actively encourages and supports women, we can harness the full potential of all professionals, thus ensuring the ongoing progress and advancement of nuclear medicine.

Estructura conceptual de la competencia gestión de desechos radiactivos para tecnólogos de Medicina Nuclear / Conceptual structure of the radioactive waste management competency for Nuclear Medicine technologists

Introducción: la Medicina Nuclear es una especialidad médica que trata o diagnostica diferentes afecciones mediante imágenes de tipo funcional-molecular, a partir del empleo de fuentes no selladas. Un aspecto importante en el desempeño profesional es la adecuada gestión de sustancias que puedan resultar nocivas. Objetivo: fundamentar la estructura conceptual de la competencia gestión de desechos radiactivos. Métodos: se realizó una revisión bibliográfica con un análisis crítico reflexivo, se consideraron documentos normativos de la actividad en Medicina Nuclear, tesis, artículos y libros, publicados a partir del 2018 en español e inglés. La búsqueda fue realizada en las bases de datos SciELO durante el periodo comprendido de enero a mayo del 2023. Las palabras clave utilizadas fueron: competencias, gestión y desechos radiactivos. Fueron revisados 73 textos y se seleccionaron 20 para conformar el texto final. Resultados: se delimitaron cuatro núcleos temáticos: pertinencia de formar competencias profesionales, base teórico-metodológica, base legal y riesgos e implicaciones. Resulta evidente el insuficiente tratamiento teórico-metodológico a la gestión de desechos como actividad de los tecnólogos de Medicina Nuclear. Se propone la definición de la competencia, los problemas contextuales que aborda, ejes procesuales, criterio de desempeño y evidencias requeridas. Conclusiones: el estudio de las competencias profesionales en los tecnólogos de la salud es un campo de notable vigencia encaminado a desarrollar su profesionalización. La evidente relación establecida entre la competencia gestión de desechos radiactivos y la reducción de riesgos y accidentes, conlleva la responsabilidad de formar profesionales preparados para desempeñarse con éxito en la Medicina Nuclear.

Introduction: Nuclear Medicine is a medical specialty that treats or diagnoses different conditions through functional-molecular images, using unsealed sources. An important aspect in professional performance is the proper management of substances that may be harmful. Objective: to support the conceptual structure of the radioactive waste management competence. Methods: a bibliographic review was carried out with a reflective critical analysis, normative documents of the activity in Nuclear Medicine, theses, articles, and books, published since 2018 in Spanish and English, were considered. The search was carried out in the SciELO databases from January to May 2023. The keywords used were competencies, management and radioactive waste. 73 texts were reviewed and 20 were selected to make up the final text. Results: four topic cores were defined: relevance of training professional competencies, theoretical-methodological base, legal base and risks and implications. The insufficient theoretical-methodological treatment of waste management as an activity of Nuclear Medicine technologists is evident. The definition of the competence, the contextual problems it addresses, procedural axes, performance criteria and required evidence are proposed. Conclusions: the study of professional competencies in health technologists is a field of notable validity aimed at developing their professionalization. The evident relationship established between radioactive waste management competence and the reduction of risks and accidents entails the responsibility of training professionals prepared to perform successfully in Nuclear Medicine.

Evaluation of the contamination droplet model used for the assessment of skin dose during the manipulation of radiopharmaceuticals.

The manipulation of radiopharmaceuticals in nuclear medicine can result in the droplet contamination of operators resulting in the accumulation of a significant skin dose. Current methods to estimate this skin dose often utilise a 50µl cylindrical droplet model, which can lead to unrealistically high estimated skin doses for some radiopharmaceuticals. By conducting experiments to measure the volume of real droplets arising from simulating the manipulation of radiopharmaceuticals, this work found that 50µl is an overestimation of a realistic contamination droplet. For almost all radiopharmaceuticals considered in this work, incorporating a smaller droplet volume into skin dose simulations resulted in higher estimates of skin dose rate per unit of activity, which, when combined with appropriate activity concentrations and droplet volumes, resulted in lower skin doses for contamination droplet incidents. The results presented in this work challenge the 50µl contamination droplet volume and highlight the importance of having an accurate model when estimating the skin dose for contamination scenarios.

Monte Carlo and experimental evaluation of a Timepix4 compact gamma camera for coded aperture nuclear medicine imaging with depth resolution.

PURPOSE: We designed a prototype compact gamma camera (MediPROBE4) for nuclear medicine tasks, including radio-guided surgery and sentinel lymph node imaging with a 99mTc radiotracer. We performed Monte Carlo (MC) simulations for image performance assessment, and first spectroscopic imaging tests with a 300 µm thick silicon detector. METHODS: The hand-held camera (1 kg weight) is based on a Timepix4 readout circuit for photon-counting, energy-sensitive, hybrid pixel detectors (24.6 × 28.2 mm2 sensitive area, 55 µm pixel pitch), developed by the Medipix4 Collaboration. The camera design adopts a CdTe detector (1 or 2 mm thick) bump-bonded to a Timepix4 readout chip and a coded aperture collimator with 0.25 mm diameter round holes made of 3D printed 1-mm thick tungsten. Image reconstruction is performed via autocorrelation deconvolution. RESULTS: Geant4 MC simulations showed that, for a 99mTc source in air, at 50 mm source-collimator distance, the estimated collimator sensitivity (4 × 10-4) is 292 times larger than that of a single hole in the mask; the system sensitivity is 0.22 cps/kBq (2 mm CdTe); the lateral spatial resolution is 1.7 mm FWHM. The estimated axial longitudinal resolution is 8.2 mm FWHM at 40 mm distance. First experimental tests with a 300 µm thick Silicon pixel detector bump-bonded to a Timepix4 chip and a high-resolution coded aperture collimator showed time-over-threshold and time-of-arrival capabilities with 241Am and 133Ba gamma-ray sources. CONCLUSIONS: MC simulations and validation lab tests showed the expected performance of the MediPROBE4 compact gamma camera for gamma-ray 3D imaging.

Quality assurance in clinical dosimetry.

INTRODUCTION: Clinical dosimetry in nuclear medicine is developing fast, with an increasing number of procedures performed for a variety of therapeutic applications. In that context, the advent of CE-marked commercial clinical dosimetry software is a positive signal, as they should, in principle, optimize the workflow and increase robustness. However, they pose the problem of the evaluation of their performances, in terms of accuracy but also ease of use (user-friendliness). AIM: The aim of this presentation is to discuss the various steps required for the evaluation of clinical dosimetry procedures in general, and dosimetry software in particular. MATERIALS AND METHODS: The clinical dosimetry workflow (CDW) is the suite of steps that lead from calibration procedures to the final reporting of the clinical dosimetry procedure. The study of the CDW implemented in various software shows a age variability in the implementation of the steps that constitute the CDW, and the order of their implementation. This can be accepted, however it raises the issue of comparing software that, basically, do not do the same thing, or do things in a different order. RESULTS AND DISCUSSION: The various steps that compose the CDW have to be studied (benchmarked) using specific tools: If assessing calibrations/reconstructions can be made using phantoms filled with radioactive sources, rigid objects are not adapted to the evaluation of registration procedures. Computing anthropomorphic models can be used to verify absorbed dose calculation algorithms (for example using Monte Carlo radiation transport modelling as the gold standard). As can be seen, a range of tools of different type (test objects, models, patient data) must be used - and sometimes developed - to evaluate each step of the CDW. Finally, the end-to-end process must be benchmarked on "real" clinical data, but the price to pay is that the ground truth is not known, thereby limiting these approaches to precision rather than accuracy. CONCLUSION: Nuclear medicine dosimetry quality assurance (QA) is in its infancy. However, procedures already applied in external beam radiotherapy may be easily transposed to nuclear medicine, and it will not take decades until nuclear medicine benefits from sound, reproducible procedures that will increase the robustness of clinical dosimetry procedures.

A multi-institutional assessment of eye lens dose in nuclear medicine clinics.

AIM: The endeavor was to measure the lens dose of actively working staff in nuclear medicine departments. MATERIAL AND METHODS: This study was accomplished in three nuclear medicine sites. A total of 23 workers in nuclear medicine joined this work. Among them are 6 SPECT/ CT technologists, 6 PET/CT technologists, 3 PET/MRI technologists, 5 radiopharmacists, 2 physicists, and 1 physician. EXTDOSE Hp(3) OSL dosimeter with tissue equivalent beryllium-oxide crystal was used for lens dose measurement. All participants were asked to wear the lens dosimeter for 2 months as near to the eye level as possible. RESULTS: Pooling the dose measures together yielded an average lens dose of 1.48 ±â€…0.77 mSv for the radiopharmacy team, 1.44 ±â€…0.26 for PET/ CT technologists, 0.86 ±â€…0.45 mSv for SPECT/ CT technologists, 0.38 mSv for the sole physician administered 177Lu, and 0.45 ±â€…0.02 mSv for the physicists conducting 131I therapy. Moreover, normalizing the lens dose to the labeled activity led to a lens dose of 2.2 ±â€…1.4 µSv/GBq for the radiopharmacy team. Likewise, per administered activity: 23.8 ±â€…7.3 µSv/GBq for PET/CT and PET/MRI technologists, 12.2 ±â€…10.5 µSv/GBq 99mTc for SPECT/CT technologists, 6.0 ±â€…0.81 µSv/GBq 131I for physicists, and 3.0 µSv/GBq 177Lu for the physician. CONCLUSION: It was deduced that the annual occupational lens dose of the nuclear medicine workers varied from 2.3 to 11.5 mSv/year; however, one radiopharmacist projected annual lens dose as close to the lens equivalent dose limit (20 mSv/year) as 17.9 mSv.

ASSESSING BODY DOSE RATE CONSTANT AND EFFECTIVE BODY ABSORPTION FACTOR IN TAIWANESE REFERENCE PHANTOMS.

The self-attenuation of a patient's body is an important factor in nuclear medicine for designing radiation shielding. Taiwanese reference man (TRM) and Taiwanese reference woman (TRW) were constructed to simulate the body dose rate constant and the effective body absorption factor for 18F-FDG, 131I-NaI and 99mTc-MIBI using the Monte Carlo technique. For TRM, the maximum body dose rate constants for 18F-FDG, 131I-NaI and 99mTc-MIBI were 1.26 × 10-1, 4.89 × 10-2 and 1.76 × 10-2 mSv-m2/GBq-h, respectively, at heights of 110, 110 and 100 cm. For TRW, the results were 1.23 × 10-1, 4.75 × 10-2 and 1.68 × 10-2 mSv-m2/GBq-h at heights of 100, 100 and 90 cm. The effective body absorption factors were 32.6, 36.7 and 46.2% for TRM and 34.2, 38.5 and 48.6% for TRW. Regional reference phantoms along with the derived body dose rate constant and effective body absorption factor should be used for determining regulatory secondary standards in nuclear medicine.

Computed tomography and nuclear medicine for the assessment of coronary inflammation: clinical applications and perspectives.

There is increasing evidence that in patients with atherosclerotic cardiovascular disease (ASCVD) under optimal medical therapy, a persisting dysregulation of the lipid and glucose metabolism, associated with adipose tissue dysfunction and inflammation, predicts a substantial residual risk of disease progression and cardiovascular events. Despite the inflammatory nature of ASCVD, circulating biomarkers such as high-sensitivity C-reactive protein and interleukins may lack specificity for vascular inflammation. As known, dysfunctional epicardial adipose tissue (EAT) and pericoronary adipose tissue (PCAT) produce pro-inflammatory mediators and promote cellular tissue infiltration triggering further pro-inflammatory mechanisms. The consequent tissue modifications determine the attenuation of PCAT as assessed and measured by coronary computed tomography angiography (CCTA). Recently, relevant studies have demonstrated a correlation between EAT and PCAT and obstructive coronary artery disease, inflammatory plaque status and coronary flow reserve (CFR). In parallel, CFR is well recognized as a marker of coronary vasomotor function that incorporates the haemodynamic effects of epicardial, diffuse and small-vessel disease on myocardial tissue perfusion. An inverse relationship between EAT volume and coronary vascular function and the association of PCAT attenuation and impaired CFR have already been reported. Moreover, many studies demonstrated that 18F-FDG PET is able to detect PCAT inflammation in patients with coronary atherosclerosis. Importantly, the perivascular FAI (fat attenuation index) showed incremental value for the prediction of adverse clinical events beyond traditional risk factors and CCTA indices by providing a quantitative measure of coronary inflammation. As an indicator of increased cardiac mortality, it could guide early targeted primary prevention in a wide spectrum of patients. In this review, we summarize the current evidence regarding the clinical applications and perspectives of EAT and PCAT assessment performed by CCTA and the prognostic information derived by nuclear medicine.

What Is New in Risk Assessment in Nuclear Cardiology?

Nuclear cardiology techniques allow in-depth evaluation of cardiac patients. A body of literature has established the use of nuclear cardiology. The results obtained with traditional cameras have been reinforced by those obtained with a series of innovations that have revolutionized the field of nuclear cardiology. This article highlights the role of nuclear cardiology in the risk assessment of patients with cardiac disease and sheds light on advancements of nuclear imaging techniques in the cardiovascular field. Patient risk stratification has a key role in modern precision medicine. Nuclear cardiac imaging techniques may quantitatively investigate major disease mechanisms of different cardiac pathologies.

Internal Bremsstrahlung, the missing process in beta decay Monte Carlo simulation: The relevance in 32P Dose-Point-Kernel estimation.

PURPOSE: In nuclear medicine, Dose Point Kernels (DPKs), representing the energy deposited all around a point isotropic source, are extensively used for dosimetry and are usually obtained by Monte Carlo (MC) simulations. For beta-decaying nuclides, DPK is usually estimated neglecting Internal Bremsstrahlung (IB) emission, a process always accompanying the beta decay and consisting in the emission of photons having a continuous spectral distribution. This work aims to study the significance of IB emission for DPK estimation in the case of 32P and provide DPK values corrected for the IB photon contribution. METHODS: DPK, in terms of the scaled absorbed dose fraction, F(R/X90), was first estimated by GAMOS MC simulation using the standard beta decay spectrum of 32P, Fß(R/X90). Subsequently, an additional source term accounting for IB photons and their spectral distribution was defined and used for a further MC simulation, thus evaluating the contribution of IB emission to DPK values, Fß+IB(R/X90). The relative percent difference, δ, between the DPKs obtained by the two approaches, Fß+IB vs. Fß, was studied as a function of the radial distance, R. RESULTS: As far as the energy deposition is mainly due to the beta particles, IB photons does not significantly contribute to DPK; conversely, for larger R, Fß+IB values are higher by 30-40% than Fß. CONCLUSIONS: The inclusion of IB emission in the MC simulations for DPK estimations is recommended, as well as the use of the DPK values corrected for IB photons, here provided.

OLINDA/EXM 2-The Next-generation Personal Computer Software for Internal Dose Assessment in Nuclear Medicine.

ABSTRACT: The OLINDA/EXM version 2.0 personal computer code was created as an upgrade to the widely used OLINDA/EXM 1.0 and 1.1 codes. This paper documents the upgrades that were implemented. New decay data and anthropomorphic and biokinetic models were implemented in the software, and the software alpha and beta tested. Agreement of doses between the OLINDA/EXM codes 1 and 2 was very good. Use of the new anthropomorphic and biokinetic models results in understandable differences between the codes. Previous models were retained in the new code, and those results were identical to those in the previous code. OLINDA/EXM 2.0 represents an upgrade from version 1, with new modeling data recommended by the international community. It standardizes internal dose calculations for dose assessments in clinical trials with radiopharmaceuticals, theoretical calculations for existing pharmaceuticals, teaching, and other purposes.

ASSESSMENT OF OCCUPATIONAL EXPOSURE TO EXTERNAL RADIATION AMONG WORKERS OF THREE COMMUNITY HOSPITALS IN SENEGAL.

Occupational radiation doses of 602 medical workers from the departments of Radiology, Thoracic and cardiovascular surgery, Operating room, Nuclear medicine, Radiotherapy and cardiology were evaluated during 2017 to 2021 in three hospitals in Senegal. Each hospital was subdivided into various occupational groups. Whole-body doses Hp(10), local skin doses Hp(0.07) and annual collective dose Hp(10) were measured by OSL (optically stimulated luminescence) dosimetry. The occupational groups with the highest radiation exposures, ~0.185 mSv in 1 y, were in the field of nuclear medicine, radiology, cardiology, Thoracic and cardiovascular surgery and Operating room. All results of the measured annual effective dose were below the ICRP (International Commission on Radiological Protection) dose limits of 20 mSv/y, averaged over any 5-y period.

Nuclear medicine in the assessment and prevention of cancer therapy-related cardiotoxicity: prospects and proposal of use by the European Association of Nuclear Medicine (EANM).

Cardiotoxicity may present as (pulmonary) hypertension, acute and chronic coronary syndromes, venous thromboembolism, cardiomyopathies/heart failure, arrhythmia, valvular heart disease, peripheral arterial disease, and myocarditis. Many of these disease entities can be diagnosed by established cardiovascular diagnostic pathways. Nuclear medicine, however, has proven promising in the diagnosis of cardiomyopathies/heart failure, and peri- and myocarditis as well as arterial inflammation. This article first outlines the spectrum of cardiotoxic cancer therapies and the potential side effects. This will be complemented by the definition of cardiotoxicity using non-nuclear cardiovascular imaging (echocardiography, CMR) and biomarkers. Available nuclear imaging techniques are then presented and specific suggestions are made for their application and potential role in the diagnosis of cardiotoxicity.

Technical note: The contribution of internal bremsstrahlung to the 90 Y dose point kernel.

BACKGROUND: Internal dosimetry has an increasing role in the planning and verification of nuclear medicine therapies with radiopharmaceuticals. Dose Point Kernels (DPKs), quantifying the energy deposition all around a point source, in a homogenous medium, are extensively used for 3D dosimetry and nowadays are mostly evaluated by Monte Carlo (MC) simulation. To our knowledge, DPK for beta emitters is estimated neglecting the continuous photon emission due to the Internal Bremsstrahlung (IB), whose contribution to the absorbed dose can be relevant beyond the maximum range of betas, as evidenced in recent works. PURPOSE: Aim of this study was to investigate and quantify, by means of MC simulations, the contribution of IB photons to DPK calculated for 90 Y and provide the updated 90 Y DPK. METHODS: The overall radiation due to the decay of a 90 Y point source, placed at the centre of concentric water shells of increasing radii from 0.02 cm to 20 cm, was simulated with GAMOS, including the IB source term whose spectral distribution was described by an analytical model. Energy deposition was scored in the shells as a function of the distance from the source, R, and DPK was estimated in terms of the scaled absorbed dose fraction, F(R/X90 ), where X90 is the range within which the beta particles deposit 90% of their energy. RESULTS: A comparison between the two simulated absorbed dose distributions, calculated with or without IB, clearly shows that the latter (incomplete) choice is consistent with the findings of other Authors and systematically underestimates the absorbed dose imparted to the tissue. 90 Y DPK values currently used are underestimated by 20%-34% for R>2X90 . CONCLUSIONS: The revised values provided in this work suggest that the inclusion of IB emission in DPK evaluations is advisable for pure beta emitters.

Accelerated Fellowships Applicable Across all Subspecialty Areas of Diagnostic Radiology as a Catalyst for Academic Recruitment.

RATIONALE AND OBJECTIVES: To build a sustainable faculty development program based on potential acceleration of all subspecialty fellowships types into the PGY 5 year. MATERIALS AND METHODS: Single center experience in programmatic change to enhance faculty recruitment. Diagnostic Radiology (DR) residents apply to subspecialty fellowships per SCARD Fellowship Embargo Guidelines. Based on projected faculty hiring needs, internal candidates are vetted and agree to enter an accelerated fellowship. The commitment is two years: the PGY5 senior year schedule prioritizes rotations in the subspecialty area while fulfilling requirements of all DR graduates, including call. Accelerated fellows (AF) participate in junior faculty development and concentrated mentoring. A subsequent instructor faculty year within our department is required to ensure professional maturity and provides financial remuneration greater than PGY 6 fellowships. RESULTS: From July 1, 2018, to June 30, 2022, 34 trainees have graduated from our DR program, and 32 have gone through the process of securing fellowships. Over this interval, our DR program has matched 7-9 residents per year. Up to four early specialization positions consisting of 2 Early Specialization in Interventional Radiology (ESIR), and 2 Early Specialization in Nuclear Medicine (ESNM), per year, are available. Over four years of the program, 8 residents participated in standard early specialization opportunities: 5 ESIR, and 3 ESNM. These 8 residents were excluded from consideration for AFs. Two additional residents declined fellowships, leaving 22 seeking standard fellowships for PGY 6 year. 6 (27%) of those were approached as potential AFs; 3 (50%) agreed to and completed the 24-month process. 2 of 3 (67%) continue to serve on faculty after the required instructor year. CONCLUSION: The novel concept of early specialization outside of ESIR and ESNM presents an opportunity to tailor the PGY 5 DR year to increase recruitment to academic faculty positions.

GATE/Geant4-based dosimetry for ex vivo in solution irradiation of blood with radionuclides.

To establish a dose-response relationship between radiation-induced DNA damage and the corresponding absorbed doses in blood irradiated with radionuclides in solution under ex vivo conditions, the absorbed dose coefficient for 1 ml for 1 h internal ex vivo irradiation of peripheral blood (dBlood) must be determined. dBlood is specific for each radionuclide, and it depends on the irradiation geometry. Therefore, the aim of this study is to use the Monte Carlo radiation transport code GATE/Geant4 to calculate the mean absorbed dose rates for ex vivo irradiation of blood with several radionuclides used in Nuclear Medicine. METHODS: The Monte Carlo simulation reproduces the irradiation geometry of a blood sample of 7 ml mixed with 1 ml of a water equivalent radioactive solution in an 8 ml vial. The simulation was performed for ten different radionuclides: 18F, 68Ga, 90Y, 99mTc, 123I, 124I, 131I, 177Lu, 223Ra, and 225Ac. Two sets of simulations for each radionuclide were performed with 1x109 histories. The first set was simulated with a mass density of 1.0525 g/cm3 of the blood plus water mixture. The second set of simulations was performed with a mass density of 1 g/cm3 for comparison with previous studies. RESULTS: The values of dBlood for ten radionuclides were calculated. The values range from 10.23 mGy∙ml∙MBq-1 for 99mTc to 15632.02 mGy∙ml∙MBq-1 for 225Ac. The maximum relative change compared to previous studies was 13.0% for 124I. CONCLUSION: This study provides a comprehensive set of absorbed dose coefficients for 1 ml for 1 h internal ex vivo irradiation of peripheral blood in a special vial geometry and radionuclides typically used in Nuclear Medicine. Furthermore, the method proposed by this work can be easily adapted to a variety of internal irradiation conditions and serve as a reference for future studies.

The potential of a medium-cost long axial FOV PET system for nuclear medicine departments.

PURPOSE: Total body positron emission tomography (TB-PET) has recently been introduced in nuclear medicine departments. There is a large interest in these systems, but for many centers, the high acquisition cost makes it very difficult to justify their current operational budget. Here, we propose medium-cost long axial FOV scanners as an alternative. METHODS: Several medium-cost long axial FOV designs are described with their advantages and drawbacks. We describe their potential for higher throughput, more cost-effective scanning, a larger group of indications, and novel research opportunities. The wider spread of TB-PET can also lead to the fast introduction of new tracers (at a low dose), new methodologies, and optimized workflows. CONCLUSIONS: A medium-cost TB-PET would be positioned between the current standard PET-CT and the full TB-PET systems in investment but recapitulate most advantages of full TB-PET. These systems could be more easily justified financially in a standard academic or large private nuclear medicine department and still have ample research options.

Technical note: Assessment of radiation measurement devices for the detection of [177 Lu]Lu-labeled radiopharmaceuticals containing [177m Lu]Lu-impurities.

BACKGROUND: Nuclear medicine therapies using [177 Lu]Lu-labeled radiopharmaceuticals have increased significantly in recent years. Some of these radiopharmaceuticals contain long-lived impurities of [177m Lu]Lu. Identification of this specific contamination and its quantification is important in different scenarios. PURPOSE: In this study, standard measurement hardware used for handling radioisotopes was evaluated for the measurement of [177m Lu]Lu and [177 Lu]Lu at equilibrium. Device-specific detection limits (LODs) for [177m Lu]Lu were determined according to international standards and then validated. METHODS: The LODs were determined according to the international standard ISO 11929-1 for [177m Lu]Lu for five identical portable contamination monitors (PCMs), a wastewater counter (WWC), and a release counter system (RCS) at different measuring times. Subsequent activity measurements of the defined samples were used to validate the linearity of the measurement instruments down to the LOD for each system. RESULTS: The average LOD across all PCMs was 0.249 ± 0.009 and 0.129 ± 0.005 Bq/cm2 for 10 and 30 s measurements, respectively. The LODs of WWC varied between 3.3 and 4.7 Bq/L for measurement times of 300 s and 0.8-1.3 Bq/L for 3600 s depending on the energy window studied. The LOD of the RCS depended on the container volume and was 0.08 Bq/g for the 50 L container at 60 s measurement. The measurements for all examined devices were linear down to the LOD (correlation coefficient R ≥ 0.96; coefficient of determination R2  ≥ 0.92). CONCLUSIONS: All investigated measuring instruments (PCM, WWC, RCS) were suitable for the determination of [177m Lu]Lu at equilibrium, and their specific LODs were determined. Based on the measurements performed, activity is overestimated; however, this is tolerable because assumptions and measurements in the context of radiation protection should be conservative.

SFE-AFCE-SFMN 2022 consensus on the management of thyroid nodules: Epidemiology and challenges in the management of thyroid nodules.

The SFE-AFCE-SFMN 2022 consensus deals with the management of thyroid nodules, a condition that is a frequent reason for consultation in endocrinology. In more than 90% of cases, patients are euthyroid, with benign non-progressive nodules that do not warrant specific treatment. The clinician's objective is to detect malignant thyroid nodules at risk of recurrence and death, toxic nodules responsible for hyperthyroidism or compressive nodules warranting treatment. The diagnosis and treatment of thyroid nodules requires close collaboration between endocrinologists, nuclear medicine physicians and surgeons, but also involves other specialists. Therefore, this consensus statement was established jointly by 3 societies: the French Society of Endocrinology (SFE), French Association of Endocrine Surgery (AFCE) and French Society of Nuclear Medicine (SFMN); the various working groups included experts from other specialties (pathologists, radiologists, pediatricians, biologists, etc.). This section deals with epidemiology and challenges in the management of thyroid nodules.

Nuclear medicine imaging methods as novel tools in the assessment of pulmonary drug disposition.

INTRODUCTION: Drugs for the treatment of respiratory diseases are commonly administered by oral inhalation. Yet surprisingly little is known about the pulmonary pharmacokinetics of inhaled molecules. Nuclear medicine imaging techniques (i.e. planar gamma scintigraphy, single-photon emission computed tomography [SPECT] and positron emission tomography [PET]) enable the noninvasive dynamic measurement of the lung concentrations of radiolabeled drugs or drug formulations. This review discusses the potential of nuclear medicine imaging techniques in inhalation biopharmaceutical research. AREAS COVERED: (i) Planar gamma scintigraphy studies with radiolabeled inhalation formulations to assess initial pulmonary drug deposition; (ii) imaging studies with radiolabeled drugs to assess their intrapulmonary pharmacokinetics; (iii) receptor occupancy studies to quantify the pharmacodynamic effect of inhaled drugs. EXPERT OPINION: Imaging techniques hold potential to bridge the knowledge gap between animal models and humans with respect to the pulmonary disposition of inhaled drugs. However, beyond the mere assessment of the initial lung deposition of inhaled formulations with planar gamma scintigraphy, imaging techniques have rarely been employed in pulmonary drug development. This may be related to several technical challenges encountered with such studies. Considering the wealth of information that can be obtained with imaging studies their use in inhalation biopharmaceutics should be further investigated.