AAPM Task Group 108: PET and PET/CT Shielding Requirements

Madsen, Mark T.; Anderson, J. A.; Halama, J; Kleck, Jeff; Simpkin, Douglas J.; Votaw, John R.; Wendt, Richard; Williams, Lawrence E.; Yester, Michael V.

doi:10.1118/1.2135911

Cited by 107 publications

(112 citation statements)

References 20 publications

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“…At 1.35 m from the phantom, the 89 Zr dose rate was estimated to be 6.04310 22 Since the injected activity of a radionuclide depends on its application, this amount varies from radionuclide to radionuclide and from examination to examination. A typical injected activity of 18 F-FDG ranges from 250 MBq [20] to 500 MBq [11], whereas the typical injected activity of 89 Zr is around 75 MBq [13]. Figure 3 shows the effective dose per scan under those conditions.…”

Section: Simulationsmentioning

confidence: 99%

“…Elschot et al [8] studied the shielding requirement of a PET/CT facility using Monte Carlo methods with the MCNPX code [9] and the Medical Internal Radiation Dose full body phantom [10]. They found that the self-absorption of 18 F-FDG emission by the patient's body reduced the dose to the clinical staff by a factor of 0.36-similar to the American Association of Physicists in Medicine (AAPM) recommendation [11], but the recommendation also overestimated the shielding requirements.…”

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Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89

Alzimami¹,

K²

2013

BJR

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Cite this article as: Alzimami KS, Ma AK. Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89. Br J Radiol 2013;86: 20130318. FULL PAPER Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89 1 K S ALZIMAMI, PhD F-FDG to the staff near the patient. This interesting result raises apparently contradictory implications in the radiation protection considerations of a PET/CT facility. Advances in knowledge: To the best of our knowledge, radiation exposure to staff and public in the PET/CT unit using 89 Zr has not been investigated. The ultimate output of this study will lead to the optimal design of the facility for routine use of 89 Zr.Positron emission tomography (PET)/CT scanners have quickly become the preferred technology for PET imaging, as the integration of functional PET images with the anatomical visualisation of CT has allowed more accurate diagnosis [1]. However, the doses delivered to patients and staff owing to the procedure should be considered and should be kept as low as reasonably achievable (ALARA) [2-4], i.e. the dose of a classified staff member should not exceed one-third of the annual dose limit.Radiation exposure of technical staff operating PET units with the use of fluorine-18 fludeoxyglucose ( 18 F-FDG) has been a controversial issue in the use of high-energy photons (511 keV), added to by a sharp increase in the number of scans undertaken using a limited number of PET/CT facilities [5][6][7]. However, the doses received by staff in PET/ CT procedures may vary considerably among facilities depending on the practices, positron emitter used, facility layout, injected activities and patient workload. Lately, several studies [5][6][7] have been carried out to assess and optimise radiation exposure to staff in the PET/CT unit when using 18 F-FDG and these studies were in agreement with a slight variation owing to different facilities and unit design. Alsafi et al [5] showed that an average staff dose per patient is 5.762.7 and 5.061.7 mSv per procedure for mobile and static facilities, respectively, using 18 F-FDG. The study of Al-Haj et al [6] reported that the estimated dose at the waiting area was 0.8 mSv per procedure. Dalianis et al [7] showed that the staff (nurse) dose during injection was in the range of 2.7-4.0 mSv and the dose to the technologist during positioning was in the range of 3.5-5.0 mSv over 10 months. Al-Haj et al [6] revealed that the estimated doses to staff working in PET/CT were within safe limits but would increase with patient workload and stay time. The 21 annual increase in patient workload necessitates that staff dose estimation be done and the protocol be reviewed for possible decrease in the 18 F-FDG activity to be administered. Elschot et al [8] studied the shielding requirement of a PET/CT facility using Monte Carlo methods with the MCNPX code [9] and the Medical Internal Radiation Dose full body phantom [10]. They found that the self-absorption of 18 F-FDG emission by ...

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Section: Simulationsmentioning

confidence: 99%

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confidence: 99%

Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89

Alzimami¹,

K²

2013

BJR

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“…O pósitron segue até colidir com um elétron e, como elétron e pósitron são antipartículas, a colisão entre eles resulta em aniquilação mútua, produzindo dois fótons em sentidos opostos e com 511 keV cada, como esquematizado na figura 1. Radioisótopos emissores de pósitrons utilizados em imagens médicas geralmente têm meias-vidas curtas, como mostra tabela 1, a seguir, e consequentemente, muitos deles, como O-15, N-13, e C-11, têm de ser produzidos com um cíclotron no local do exame, a fim de dispor de quantidades clinicamente úteis 3 Atualmente, o radionuclídeo mais utilizado na técnica de PET/CT é o 18F, marcando a fluordeoxiglicose (FDG), um análogo da glicose que é consumido por células ativas, de tal maneira que sua presença indica função metabólica tecidual. Os quase 110 minutos de meia-vida do 18F permitem que a FDG marcada seja transportada a locais de exame razoavelmente afastados do centro de produção (em torno de 100 km por transporte terrestre), de modo que a PET realizada com FDG é dominante, com aplicações principalmente em oncologia e, em menor extensão, em neurologia, psiquiatria e cardiologia 4 .…”

Section: Introductionunclassified

Aplicativo DosedPet para uso em Medicina Nuclear: Cálculo do volume de medicamento necessário para paciente de PET/CT.

Nascimento

Rodrigues

2016

Rev Bras Fis Med

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ResumoNesse trabalho, apresentamos o Aplicativo (APP) DosePet que tem por objetivo o cálculo do volume por meio da atividade das doses administradas a pacientes de PET/CT. O software foi projetado utilizando a ferramenta Web MIT App Inventor2 para plataforma Android. O aplicativo permite avaliar a quantidade de radiação ainda existente nas instalações após as aplicações, aumentando a segurança e diminuindo as exposições, além de possibilitar maior eficiência no aproveitamento do radiofármaco. Palavras-chaves: Dose PET/CT; física médica; aplicativo. Abstract This paper presents the application (APP) DosePet that calculates the amount of medicament for PET / CT in patients according to the predetermined radiation dose. The software has been designed using the web MIT App Inventor2 tool for Android platform. The application allows the workers to simulate the amount of radiation still existing in the facilities after the applications, increasing security and reducing exposures, and enable greater efficiency in the use of the radiopharmaceutical.

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“…The published study by Brinkley et al (2009) evaluated the influence of the scatter in the patient and had identified that the fraction of lower energies is significant compared to 511 keV photons and can influence the effective attenuation of lead in clinical PET facilities. In order to find optimized shielding barriers, different authors have published information regarding the transmission curves (Demir and Keles, 2006;Elschot et al, 2010;Madsen et al, 2006). Many published papers have been used Monte Carlo toolkits to generate those data and to explore different possibilities for transmission curves (Brinkley et al, 2009;Cruzate and Discacciatti, 2008;Hoff et al, 2010;Madsen et al, 2006).…”

Section: Introductionmentioning

confidence: 99%

A comparative study for different shielding material composition and beam geometry applied to PET facilities: simulated transmission curves

Hoff

Costa

2013

RBEB

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The aim of this work is to simulate transmission data for different beam geometry and material composition in order to evaluate the effect of these parameters on transmission curves. The simulations are focused on outgoing spectra for shielding barriers used in PET facilities. The behavior of the transmission was evaluated as a function of the shielding material composition and thickness using Geant4 Monte Carlo code, version 9.2 p 03.The application was benchmarked for barited mortar and compared to The American Association of Physicists in Medicine (AAPM) data for lead. Their influence on the transmission curves as well the study of the influence of the shielding material composition and beam geometry on the outgoing spectra were performed. Characteristics of transmitted spectra, such as shape, average energy and Half-Value Layer (HVL), were also evaluated. The Geant4 toolkit benchmark for the energy resulting from the positron annihilation phenomena and its application in transmission curves description shown good agreement between data published by American Association on Physicists in Medicine task group 108 and experimental data published by Brasil. The transmission properties for different material compositions were also studied and have shown low dependency with the considered thicknesses. The broad and narrow beams configuration presented significant differences on the result. The fitting parameter for determining the transmission curves equations, according to Archer model is presented for different material. As conclusion were defined that beam geometry has significant influence and the composition has low influence on transmission curves for shielding design for the range of energy applied to PET.

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AAPM Task Group 108: PET and PET/CT Shielding Requirements

Cited by 107 publications

References 20 publications

Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89

Effective dose to staff members in a positron emission tomography/CT facility using zirconium-89

Aplicativo DosedPet para uso em Medicina Nuclear: Cálculo do volume de medicamento necessário para paciente de PET/CT.

A comparative study for different shielding material composition and beam geometry applied to PET facilities: simulated transmission curves

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