The international reference system for beta-particle emitting radionuclides: Validation through the pilot study CCRI(II)-P1.Co-60.

The Bureau International des Poids et Mesures (BIPM) is developing a new transfer instrument to extend its centralized services for assessing the international equivalence of radioactive standards to new radionuclides. A liquid scintillation counter using the triple/double coincidence ratio method is being studied and tested in the CCRI(II)-P1.Co-60 pilot study. The pilot study, involving 13 participating laboratories with primary calibration capabilities, validated the approach against the original international reference system based on ionization chambers, which has been in operation since 1976. The results are in agreement and an accuracy suitable for purpose, below 5×10-4, is achieved. The pilot study also reveals an issue when impurities emitting low-energy electrons are present in the standard solution, which have a different impact on liquid scintillation counting compared to other primary measurement methods.

Evaluation of the efficiency curve of a Cadmiun Telluride detector for low-energy photon spectrometry.

The performance of a Cadmiun Telluride (CdTe) detector for low energy photon spectrometry was evaluated. Collected data were analyzed using the basic software package available with the CdTe detector system and the COLEGRAM code developed for photopeak deconvolution at LNHB/France. Several calibrated point sources were used to determine the energy versus efficiency curve. The efficiency curve was used in the determination of main X-ray intensities of (153)Sm and (177)Lu.

Primary activity standardization of 99Tc by three different absolute methods.

The activity concentration of a solution of (99)Tc was absolutely determined by liquid scintillation measurements based on the triple-to double-coincidence ratio method (TDCR) and compared with the results given by 4πß(LS)-γ(NaI) live-timed anticoincidence (with extending dead-time) and classical 4πß(PC)-γ(NaI) coincidence counting systems based on using (60)Co as the efficiency-tracing radionuclide. The results of anticoincidence and coincidence counting are, respectively, 0.18% and 0.66% higher than the result from TDCR measurements, but they are consistent within uncertainties.

Fatores de correção volumétrica na medição de atividade de 99mTc e 123I em calibradores de radionuclídeos / Volume corrections factors in the measurement of 99mTc and 123I activities in radionuclide calibrators

OBJETIVO: Determinar os fatores de correção para a variação volumétrica dos radiofármacos contidos em recipientes de diferentes geometrias. Comparar a influência desses fatores na determinação da atividade de 99mTc e 123I utilizando dois tipos de calibradores: um com câmara de ionização e outro com detector Geiger-Müller (G-M). Avaliar o desempenho de calibradores de alguns serviços de medicina nuclear em medição de atividade de 99mTc e 123I. MATERIAIS E MÉTODOS: Foram utilizados oito calibradores, frascos de vidro 10R, seringas de plástico de 3 e 5 mL e soluções de 99mTc e 123I. Os fatores de correção foram determinados a partir das medições práticas da variação da leitura do calibrador com a variação do volume da solução no recipiente. O desempenho foi avaliado em relação ao critério de aceitação de ±10% de exatidão exigida pela norma brasileira. RESULTADOS: A variação da resposta do calibrador com a variação do volume do frasco foi bem maior no calibrador que utiliza G-M. Ela também foi maior para 123I do que para 99mTc. CONCLUSÃO: Os resultados confirmam que a resposta dos calibradores depende do volume contido nos recipientes. Essa dependência é mais crítica para os calibradores equipados com detector G-M e para 123I quando comparado com 99mTc.

OBJECTIVE: To determine correction factors for the variation in volume of radiopharmaceuticals in containers of different geometries, comparing the influence of such factors on the determination of 99mTc and 123I activity with two types of calibrators - one with ionization chamber and another with Geiger-Müller (G-M) detector -; and to evaluate calibrators performance in the measurement of 99mTc and 123I activities. MATERIALS AND METHODS: Eight calibrators, 10R glass vials, 3 and 5 mL plastic syringes and 99mTc and 123I solutions were utilized. The correction factors were determined with basis on practical measurements of the variation in the calibrators' response according to the volume of radionuclide solution in the glass vials. The performance was evaluated according to the acceptance criterion of ±10% accuracy required by the Brazilian standard. RESULTS: The variation of the calibrators' response according to the variation in radionuclide volume was reasonably greater in the calibrator with G-M detector. It was also greater for 123I than for 99mTc. CONCLUSION: The results confirm that the calibrators' response depends on the radionuclide volume contained in the vials. Such dependence is more critical for the calibrators equipped with G-M detector and for 123I as compared with 99mTc.

Comparison of activity measurements in nuclear medicine services in Pernambuco

Intercomparison is an important tool for quality assessment, because equipment performance and procedures are evaluated and compared. In nuclear medicine, this tool is wide utilized to evaluate the ability of the services to measure activities of radiopharmaceuticals which will be administered to the patients in diagnostic or therapeutic procedures. In this work, a comparison program of activity measurements of the 99mTc, 131I, 67Ga and 201Tl radionuclides was established in Pernambuco State, at the Brazilian Northeast, with the aim of evaluating the quality of routine measurements carried out in the NMS. The results in each NMS are sent to the Standard laboratory, which compares these results with the acceptance limits recommended by national regulations. All NMS participants complied with the limit established for the accuracy of measurement (+/-10 percent) and showed that their radionuclide calibrators are adequate for measurement of the activities of radiopharmaceuticals.

A intercomparação é uma importante ferramenta para avaliação da qualidade da medição da atividade de radiofármaco, porque não apenas o desempenho do equipamento é verificado, mas também todo procedimento de medição. Na medicina nuclear, esta ferramenta é amplamente utilizada para avaliar a habilidade dos serviços de medicina nuclear (SMN) na medição da atividade dos radiofármacos que serão administrados aos pacientes para diagnósticos ou procedimentos terapêuticos. Neste trabalho, um programa de intercomparação de medidas de atividades de radiofármacos, utilizando as fontes de 99mTc, 131I, 67Ga e 201Tl, foi estabelecido no estado de Pernambuco, região nordeste do Brasil, com o objetivo de avaliar a qualidade das medições realizadas nos SMN. Os resultados obtidos em cada SMN são enviados ao laboratório padrão, que os compara com os valores de referência recomendados pela norma nacional, verificando o desempenho destes instrumentos. Todos os SMN participantes respeitaram os limites estabelecidos para a exatidão das medidas (+/-10 por cento), demonstrando que os calibradores de radionuclídeos estão adequados/apropriados para a medição de atividades de radiofármacos.

National comparison of 131I measurement among nuclear medicine clinics of eight countries.

A generally applicable protocol for organizing comparisons among nuclear medicine clinics created within the IAEA project CRP E2.10.05 was tested in Brazil, Cuba, Czech Republic, India, Iran, Republic of Korea, Romania and Turkey in 2007. Comparisons of measurement of (131)I were organized by local pilot laboratories with different backgrounds and levels of experience in this field. The results and experiences gained were compared and analyzed. A majority of results in each national comparison were within 10% of the reference value.

Teste de proficiência para medições de radioatividade na medicina nuclear / Proficiency test for radioactivity measurements in nuclear medicine

OBJETIVO: Avaliar o desempenho dos calibradores de radionuclídeos de 55 serviços de medicina nuclear brasileiros em medição de atividade de radiofármaco contendo 99Tc m. Testes de proficiência foram aplicados em 63 resultados originados do programa de comparação promovido pelo Laboratório Nacional de Metrologia das Radiações Ionizantes do Instituto de Radioproteção e Dosimetria. MATERIAIS E MÉTODOS: O desempenho foi avaliado em relação ao critério de aceitação de ±10 por cento de exatidão exigido pela norma brasileira e também aos critérios estabelecidos pela ISO/IEC Guide 43-1, e classificado como "aceitável" ou "não aceitável". Amostras de 99Tc m usadas nas comparações foram fornecidas por alguns dos participantes e calibradas no Laboratório Nacional de Metrologia das Radiações Ionizantes para determinar o valor de referência da atividade. RESULTADOS: Esta comparação com o 99Tc m mostrou que o desempenho aceitável atendendo à exigência da norma regulatória foi de 82,5 por cento, enquanto pelos critérios estabelecidos pela norma ISO/IEC 43-1 foi de 81,0 por cento. Por outro lado, calibradores de radionuclídeos com detector Geiger-Müller apresentaram desempenho inferior quando comparados com os dotados com câmara de ionização. CONCLU-SÃO: Nesta comparação, a avaliação do desempenho baseada nos critérios da ISO/IEC 43-1, os quais são aplicados a laboratórios analíticos, apesar de serem mais restritivas, foi bastante consistente com o critério de exatidão exigido pela norma nacional.

OBJECTIVE: To assess the performance of radionuclide calibrators in 55 Brazilian nuclear medicine services in the measurement of 99Tc m radiopharmaceutical activity. Proficiency tests were applied to data sets with 63 results originated from the comparison program developed by Laboratório Nacional de Metrologia das Radiações Ionizantes of Instituto de Radioproteção e Dosimetria. MATERIALS AND METHODS: The calibrators' performance was evaluated in compliance with the acceptance criterion of ±10 percent accuracy required by the Brazilian standards and also the criteria established by the ISO/IEC Guide 43-1, and classified as either "acceptable" or "non-acceptable". The samples of 99Tc m utilized in the comparison were supplied by some of the participants and calibrated at Laboratório Nacional de Metrologia das Radiações Ionizantes for determining the activity reference value. RESULTS: The present study utilizing 99Tc m has shown that 82.5 percent of the calibrators were considered as acceptable according to the Brazilian standards, while by the criteria established by ISO/IEC 43-1, 81.0 percent were considered as acceptable. On the other hand, radionuclide calibrators with Geiger-Müller detectors presented unsatisfactory performance when compared with calibrators with ionization chambers. CONCLUSION: The performance evaluation based on the ISO/IEC 43-1 criteria, which are applied to analytical laboratories, in spite of being more restrictive, has demonstrated to be quite consistent with the accuracy criterion established by the Brazilian standard.

Comparación de la medición de actividad de 131I con activímetros en medicina nuclear en cuba / Comparison of 131I activity measurements with radionuclide calibrators in nuclear medicine in cuba

Se presentan los resultados de la comparación nacional de la medición de actividad de 131I con activímetros, organizada en Cuba en el 2007. Estos resultados contribuyen a establecer la incertidumbre y la trazabilidad de los valores de actividad de 131I, determinados en los activímetros de las diferentes instituciones participantes: 9 hospitales y dos laboratorios del Centro de Isótopos que participaron directamente en la producción de los radiofármacos. Si consideramos solamente la proporción de resultados satisfactorios, el desempeño evidenciado por los participantes es igual al alcanzado en las comparaciones de este tipo, organizadas del 2002 al 2004 en el país. No obstante, la estimación razonable de la incertidumbre de la actividad de 131I medida en el activímetro, realizada por la mayoría de los participantes en el 2007, muestra un resultado cualitativamente superior con respecto al obtenido en el 2002-2004. Se reportaron los resultados del ejercicio bilateral de medición de 131I entre el Departamento de Metrología de Radionúclidos del Centro de Isótopos y el Laboratorio Nacional de Metrología de las Radiaciones Ionizantes del Instituto de Protección Radiológica y Dosimetría de Brasil. Concebido como complemento de la comparación nacional, este ejercicio bilateral proporciona evidencias adicionales de la comparabilidad de los patrones de medición utilizados para calibrar las disoluciones y muestras de referencia de 131I en el Departamento de Metrología de Radionúclidos del Centro de Isótopos.

Results from the national comparison of 131I activity measurements with radionuclide calibrators in Nuclear Medicine, organized in Cuba in 2007, are shown. These results contribute to establish the uncertainty and traceability of the 131I activity values measured with radionuclide calibrators of the participating institutions: 9 hospitals and two laboratories of the Isotope Centre directly involved in radiopharmaceuticals’ production. Concerning the proportion of acceptable results, no improvement was observed in the participants’ performance compared to results shown in such kind of exercises organized in the country during 2002-2004. On the other hand, the reasonable uncertainty estimate of the 131I measurements reported by most of the participants show a qualitatively superior outcome in 2007 compared to the result obtained in the previously organized exercises. Moreover, the outcome of the bilateral comparison for 131I activity measurements between the Radionuclide Metrology Department of the Isotope Centre (CENTIS-DMR) and the National Metrology Laboratory for Ionizing Radiation of the Brazilian Institute of Radiation Protection and Dosimetry (LNMRI-IRD) is also shown. This bilateral exercise provides additional evidences on comparability of the CENTIS-DMR measurement standards used to calibrate 131I reference solutions and samples.

Proficiency tests in the determination of activity of radionuclides in radiopharmaceutical products measured by nuclear medicine services in 8 years of comparison programmes in Brazil.

Proficiency tests were applied to assess the performance of 74 nuclear medicine services in activity measurements of (131)I, (123)I, (99)Tc(m), (67)Ga and (201)Tl. These tests produced 913 data sets from comparison programmes promoted by the National Laboratory for Ionizing Radiation Metrology (LNMRI) from 1999 to 2006. The data were evaluated against acceptance criteria for accuracy and precision and assigned as Acceptable or Not acceptable accordingly. In addition, three other statistical parameters were used as complementary information for performance evaluation which related to normative requirements and to radionuclide calibrators. The results have shown a necessity to improve quality control procedures and unsatisfactory performances of radionuclide calibrators, which incorporate Geiger-Müller detectors.

Implementation of a national metrology network of radionuclides used in nuclear medicine.

The Nuclear Medicine Services (NMS) in Brazil routinely use dose calibrators to measure the activity of solutions containing radiopharmaceuticals. These solutions are administered to patients with the intention to diagnose or treat illnesses. However, for optimal results, the activity of these radiopharmaceuticals must be determined as accurately as possible. The National Laboratory for Ionizing Radiation Metrology (LNMRI) led, since 1998, a comparison program for activity measurements of radiopharmaceuticals administered to patients in the NMS with the purpose promoting quality control. This program has been carried out successfully in Rio de Janeiro, but there is a need to implement it around the country. This can be resolved through the implementation of a network of regional laboratories at various locations throughout the national territory. Currently, such a network is active at a second site, located in Brasília, covering the needs of the Center-West Region, and at a third site, located in Porto Alegre, in the South Region. This work presents the results of comparisons for the radiopharmaceuticals nuclides 131I and 99Tcm and proves that the implementation of a radionuclide metrology network is feasible and viable.

Determination of disintegration rates and gamma-ray emission probabilities of 65Zn and 241Am.

Radioactive solutions of (65)Zn and (241)Am were standardized within the frame of the CCRI (II)/BIPM key comparisons carried out recently in 2003. The activity concentrations (in Bqg(-1)) were determined using the 4pi(proportional counter)-gamma coincidence counting method with efficiency extrapolation. Liquid scintillation methods were also used for (241)Am activity determination. The 1115.5 keV of (65)Zn and the 26.35 and 59.54 keV of (241)Am gamma-ray emission probabilities were determined as 0.4971, 0.0206 and 0.3587, respectively, using a planar germanium detector. The associated relative uncertainties were 0.33%, 1.56% and 0.47%, respectively.

The absolute standardization of 32P and 204Tl at LNMRI.

32P and 204Tl solutions were standardized within the frame of the international key comparisons organized by bureau international des poids et mesures, in 2002. The activity concentration of 32P was measured by counting solid sources in a 4pibeta proportional gas flow counter and by liquid scintillation counting. The self-absorption in solid sources for 4pibeta counting and the presence of 33P as an impurity were evaluated. The combined standard uncertainty for 32P was 0.59% in the 4pibeta counting and 0.38% in the liquid scintillation counting. Liquid scintillation counting was used to measure the activity concentration of 204Tl with combined standard uncertainty of 0.35%.

National intercomparison program for radiopharmaceutical activity measurements.

Since 1998, the National Laboratory for Ionizing Radiation Metrology has lead an intercomparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose of promoting the quality control. In this work, intercomparison results with the radionuclides 67Ga, 123I, 99mTc and 201Tl from the beginning of the program to the present will be presented establishing as a consequence, the radionuclide calibrators' traceability used by the participants. The analysis of the results showed that 68% were within the limits of +/-10% required by the Brazilian Regulatory Authority that demands this accuracy band for the radiopharmaceutical measurements in the NMS. The results also demonstrate an improvement in the measurement quality that this program has provided since its beginning.

Absolute determination of activity per mass and half-life measurements of 152Eu.

A solution of 152Eu was absolutely standardized by the 4pi beta (PPC)-gamma (HPGe) coincidence counting method as part of an intercomparison program coordinated by Bureau International des Poids et Mesures. The measured activity has been used to determine the calibration factor of the LNMRI reference ionization chamber for 152Eu. The half-life of 152Eu was also determined by means of a 4pi gamma ionization chamber to be (4963.6+/-15.3) days, and compared with others published values.

166mHo: a multi-gamma standard for the calibration of Ge spectrometers.

Efficiency calibration curves for germanium detectors are usually established by using a large number of standard gamma-ray sources of specific radionuclides, that decay with few gamma-rays, or radionuclides with complex decay schemes, such as 133Ba or 152Eu. But these multi-gamma radionuclides cannot be used alone, because the gamma-rays of high intensity are irregularly distributed across the energy spectrum. 166mHo is a more suitable single source for such calibrations, because this radionuclide decays by beta(-)emission to the excited states of 166Er with the subsequent emission of about 20 strong and well distributed gamma-rays ever the energy range 50-1000 keV. Moreover, with a relatively long half-life (1200 yr) and characteristic X-rays between 40 and 50 keV, this nuclide is a good standard for the calibration of germanium detectors. The X- and gamma-ray emission probabilities of their main lines need to be known with good accuracy in order to resolve the discrepancies found in the literature. A combination of 4pi beta-gamma coincidence and X- and gamma-ray spectrometric techniques have been used to determine 50 photon emission probabilities.