Simplicity or complexity of the radiopharmaceutical production process in the light of optimization of radiation protection of staff – &lt;sup&gt;99m&lt;/sup&gt;Tc vs. &lt;sup&gt;18&lt;/sup&gt;F

Wrzesień, Małgorzata

doi:10.13075/mp.5893.00687

Cited by 9 publications

(8 citation statements)

References 18 publications

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“…Previously, the authors of the present study have already investigated hand exposures due to the most popular radionuclide, 99m Tc, produced with a radionuclide generator (Wrzesień 2018). It is worth noting that compared with 18 F or 68 Ga, 99m Tc is a source of gamma radiation with an energy of 144 keV.…”

Section: Discussionmentioning

confidence: 98%

“…This is because employees typically do not only carry out the procedures of producing the radionuclides by themselves, but also label chemical compounds with these radionuclides in order to obtain radiopharmaceuticals, and/or inject the prepared radiopharmaceutical into a patient's body (Stuarto 1990;Chiesa et al 1997;Williams et al 1990;Batchelor et al 1991;Dhanse et al 2000;Kubo & Mauricio 2014;Sandouqa et al 2011;Leide-Svegborn 2011). The occupational groups most affected by this exposure are radiochemists and nurses (Meisenheimer et al 2020;Wrzesień and Napolska 2015;Wrzesień et al 2019;Wrzesień and Albiniak 2016;Wrzesień 2018;Vanhavere et al 2012). During the last decade, a lot of attention in scientific publications has been devoted to the exposure of the hands when performing tasks involving radionuclides (Sans-Merce et al 2011a;Breeman et al 2005;Wrzesień et al 2008;Carnicer et al 2011;Sans Merce et al 2011b).…”

Section: Introductionmentioning

confidence: 99%

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Personal dose equivalent Hp(0.07) during 68Ga-DOTA-TATE production procedures

Wrzesień

Albiniak

2023

Radiat Environ Biophys

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This work presents the exposure of hands of the personnel of a nuclear medicine department who prepare and administer 68Ga-DOTA-TATE. Dosimetry measurements were performed during three 1-week sessions, for nine production procedures. A total of 360 measurements were made by using high-sensitivity MCP-N thermoluminescent detectors. Annealed detectors were and vacuum-packed in foil and then placed on each fingertip of both hands of five radiochemists and four nurses (one detector for one fingertip). The greatest exposure to ionizing radiation was found on the non-dominant left hand of radiochemists and nurses. A maximum Hp(0.07)/A value of 49.36 ± 4.95 mSv/GBq was registered for radiochemists during the 68 Ga-DOTA-DATE activity dispensing procedure. For nurses performing the radiopharmaceutical injection procedure, a corresponding maximum value of 1.28 ± 0.13 mSv/GBq was measured, while the mean value for all the nurses was 0.38 mSv/GBq. The dispensing procedure accounted for approximately 60% of the total exposure of radiochemists' fingertips. Based on the results obtained it is recommended that a ring dosimeter should be routinely placed on the middle finger of the non-dominant hand of radiochemists and nurses. Furthermore, it is proposed to systematically train workers in handling open sources of ionizing radiation, with the aim of reducing the required handling time.

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Section: Discussionmentioning

confidence: 98%

Section: Introductionmentioning

confidence: 99%

Personal dose equivalent Hp(0.07) during 68Ga-DOTA-TATE production procedures

Wrzesień

Albiniak

2023

Radiat Environ Biophys

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“…The first was the choice of the hand model. For this it was important to realize that dosimetry measurements suggested that the quality control procedure and radiopharmaceutical injection have the greatest impact on the dose to the fingertips of personnel (Wrzesień et al 2016 , 2018 ; Wrzesień 2018a , b ). Taking into account the fact that 70% of employees performing the above-mentioned procedures are women, the dimensions of the female hand model were used to construct the hand model.…”

Section: Methodsmentioning

confidence: 99%

“…The measurements included highly sensitive MCP-N (LiF: Mg, Cu, P) thermoluminescence detectors manufactured by Radcard (Kraków, Poland). The detectors were calibrated in accordance with ISO 4037-3 (ISO 2019 ) as described in (Wrzesień et al 2016 , 2018 ; Wrzesień 2018a , b ; Wrzesień and Napolska 2015 ). In total, 22 workers were included in the dosimetry measurements, including four physicists, nine chemists and nine nurses.…”

Section: Methodsmentioning

confidence: 99%

Using Monte Carlo methods for Hp(0.07) values assessment during the handling of 18F-FDG

Albiniak

Wrzesień

2020

Radiat Environ Biophys

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The dose limit for the skin of the hand is typically converted to a surface of 1 cm2, which means that one needs to measure point doses in different places on the hand. However, the commonly used method of measuring doses on the hand, i.e., using a dosimetric ring including one or several thermoluminescent detectors worn at the base of a finger, is not adequate for manual procedures such as labeling or radiopharmaceutical injection. Consequently, the purpose of this study was to create and conduct a series of computer simulations that, by recreating the actual working conditions, would provide information on the values of ionizing radiation doses received by the most exposed parts of the hands of employees of radiopharmaceutical production facilities, as well as those of nurses during the injection of radiopharmaceuticals. The simulations were carried out using Monte Carlo radiation transport calculations. The Hp(0.07) personal dose equivalent values obtained for the fingertips of the index and middle fingers of nursing staff and chemists were within the range limited by the minimum and maximum Hp(0.07) values obtained as a result of dosimetric measurements carried out in diagnostic and production centers. Only in the case of the nurse’s fingertip, the simulated value of Hp(0.07 slightly exceeded the measured maximum Hp(0.07) value. The comparison of measured and simulated dose values showed that the largest differences in Hp(0.07) values occurred at the thumb tip, and for ring finger and middle finger of some of the nurses investigated.

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“…Tc‐99m is the most used radionuclide in nuclear medicine imaging because it fulfills many of the criteria of an ideal radionuclide, such as half‐life, decay mode, and photon energy. 1 , 2 , 3 In our routine practice, scintigraphic exams using Tc‐99m radiolabeled pharmaceuticals are usually acquired with a low‐energy high‐resolution (LEHR) collimator. 4 , 5 Collimator design is a compromise between spatial resolution and sensitivity.…”

Section: Introductionmentioning

confidence: 99%

Investigating the lesion detectability of Tc‐99m planar scintigraphy acquired with LEHRS collimator for patients with different body sizes: A phantom study

Lin

Jhan

et al. 2022

J Applied Clin Med Phys

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Purpose The aim of this work was to investigate the lesion detectability of Tc‐99m planar scintigraphy acquired with a low‐energy high‐resolution and sensitivity (LEHRS) collimator and processed by Clarity 2D for patients with different body sizes through phantom study. Methods A NEMA IEC body phantom set was covered by two layers of 25‐mm‐thick bolus to construct phantom in three different sizes. All image data were performed on a Discovery NM/CT 870 DR with an LEHRS collimator and processed by Clarity 2D with blend ratio a of 0%, 20%, 40%, 60%, 80%, and 100%. The lesion detectability in gamma scintigraphy was evaluated by calculating the contrast‐to‐noise ratio (CNR). Multiple linear regression methods were used to analyze the impact of body size, target size, and Clarity 2D blending weight on the lesion detectability of Tc‐99m planar scintigraphy. Results It was found that changing the blend ratio could improve CNR, and this phenomenon was more significant in anterior view than in posterior view. Our results also suggested that the blend ratio should be selected according to patient body size in order to maintain consistent CNR. Hence, when a blend ratio of 60% was used for a patient before cancer treatment, a lower blend ratio should be used for the same patient experiencing treatment‐related weight loss to achieve consistent lesion detectability in Tc‐99m planar scintigraphy acquired with LEHRS and processed by Clarity 2D. Conclusion The magnitude of photon attenuation and scattering is higher in patients with larger body size, so Tc‐99m planar scintigraphy usually has lower lesion detectability in obese patients. Although photon attenuation and scattering are inevitable during image formation, their impacts on image quality can be eased by employing appropriate image protocol parameters.

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Simplicity or complexity of the radiopharmaceutical production process in the light of optimization of radiation protection of staff – <sup>99m</sup>Tc vs. <sup>18</sup>F

Cited by 9 publications

References 18 publications

Personal dose equivalent Hp(0.07) during 68Ga-DOTA-TATE production procedures

Personal dose equivalent Hp(0.07) during 68Ga-DOTA-TATE production procedures

Using Monte Carlo methods for Hp(0.07) values assessment during the handling of 18F-FDG

Investigating the lesion detectability of Tc‐99m planar scintigraphy acquired with LEHRS collimator for patients with different body sizes: A phantom study

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