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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. [ABSTRACT FROM AUTHOR]

The climate models are extremely complex pieces of software. They reflect best knowledge on physical components of the climate, nevertheless, they contain several parameters, which are too weakly constrained by observations, and can potentially lead to a crash of simulation. Recently a study by Lucas et al. (2013) has shown that machine learning methods can be used for predicting which combinations of parameters can lead to crash of simulation, and hence which processes described by these parameters need refined analyses. In the current study we reanalyse the dataset used in this research using different methodology. We confirm the main conclusion of the original study concerning suitability of machine learning for prediction of crashes. We show, that only three of the eight parameters indicated in the original study as relevant for prediction of the crash are indeed strongly relevant, three other are relevant but redundant, and two are not relevant at all. We also show that the variance due to split of data between training and validation sets has large influence both on accuracy of predictions and relative importance of variables, hence only cross-validated approach can deliver robust prediction of performance and relevance of variables. [ABSTRACT FROM AUTHOR]

131I has been widely used in nuclear medicine for many years, particularly in the form of iodide for the diagnosis and therapy of thyroid cancer and other thyroid diseases. Manual dispensing of radioiodine-based radiopharmaceuticals results in potentially significant radiation doses to the hands of nuclear medicine personnel performing this task. This article reports the results of thermoluminescent dosemeter-based measurement of radiation doses at various points on the hands of personnel dispensing radioiodine radiopharmaceuticals. [ABSTRACT FROM AUTHOR]

In a modern agricultural landscape the assurance of food resources is a key issue in the maintaince and control of food niche for pollinators. In the present study we evaluated bee forage flora composition and diversity within railway embankments located in the agricultural landscape, SE Poland. We also analysed the abundance of pollinators that use food resources along railway embankments and recognized insect visitors preference for selected plant species. Railway embankments represent valuable refuge areas for bee forage flora (307 species, i.e. 76.1% of total flora) and pollinators (in total 4172 insect visits from 9 taxonomic groups). However, the richness and abundance of bee forage flora significantly differed between types of the railway distinguished by traffic volume. The highest diversity of bee forage flora is noted along the railway with intermediate traffic volume. Approx. 25% and 40% less bee forage species was identified along railways with low and high traffic volume. Likewise, bee forage flora differed considerably between microhabitat types, i.e. top vs. slope vs. bottom of the embankment. Providing support (e.g. mowing) seems to be an important management type in order to strengthen the native bee forage flora particularly on railway embankments along low and high traffic volume tracks. Such activity is crucial to counteract the spread of aggressive non-forage species (e.g. Calamagrostis epigejos, Artemisia vulgaris, Phragmites communis) and invasive species (e.g. Bunias orientalis, Solidago gigantea).

Understanding the factors that have an impact on the diversity of forage flora in the agricultural landscape is a key issue in the maintenance and control of food niches for pollinators. Field margins are common linear structures in the agricultural landscape. In the present study, we evaluated the factors that exert an impact on the forage flora composition and on the diversity in field margins. The study was conducted in the 2010 - 2011 time period across the agricultural landscape on the Lublin Upland of SE Poland. Data on the forage flora were obtained while making floristic charts along 45 transect plots x 300 m; the total length being 13500 m. Multivariate ordination techniques (PCA and RDA) were employed to analyse forage-flora characteristics. Field margins represent valuable refuge areas for forage-species richness, but not for the abundance of forage species. On field margins, forage-species diversity benefits from the location of natural habitats (forests or meadows), primarily if the distance from these habitats is

The mature larva and pupa of Otiorhynchus smreczynskii are described and illustrated with complete chaetotaxy for the first time. Five larval instars and the factors for larval growth are determined, and the larval development of this species is comprehensively described. In order to confirm species affiliation, selected larvae were subjected to genetic analysis (mtCOI). Host plants and unique feeding signs of some Entiminae species are presented, and all available data on development are documented and interpreted. Additionally, the morphometry of 78 specimens (48 of O. smreczynskii and 30 of O. rotundus ) was examined in order to verify the usefulness of morphological features in distinguishing both species. The female genitalia of both species are illustrated, described and compared with each other for the first time. Finally, the updated distribution of O. smreczynskii is given, and a possible origin of O. smreczynskii and O. rotundus is proposed.

Objectives: While working with cyclotrons used for the production of radiopharmaceuticals, workers can experience significant exposure to the adverse effects of ionizing radiation. The aim of this paper was to determine the typical level of such exposure received by such personnel while servicing cyclotrons., Material and Methods: Exposure was assessed using TLD detectors placed in an anthropomorphic phantom, as well as dose meter to determine whole body and eye lens exposure. The phantom was placed in locations receiving the greatest exposure to ionizing radiation during service activities. The time spent by employees during servicing was assessed based on routine visits by service technicians. The obtained results were compared with readings of detectors worn by employees during service activities., Results: The highest equivalent doses in the thoracic area were found to be received by the lungs (211.16 μSv/year). In the head and neck area, the highest dose was measured in the eye lens (3410 μSv/year). The effective dose for the whole body was found to be 1154.4 μSv/year, based on the phantom, and 149 μSv per service visit (1192 μSv/year), based on the dose meters carried by the workers., Conclusions: Service workers are exposed to significant doses of ionizing radiation, representing a clear radiological protection issue. To reduce exposure to eye lenses, it is recommended to use protective goggles when working with highly-radioactive elements. Int J Occup Med Environ Health. 2022;35(6):753-60., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

In Europe, honey bees and bumble bees are among the most important pollinators, and there is a growing interest in understanding the effects of floral resource availability on their survival. Yet, to date, data on nectar and pollen supplies available to bees in agricultural landscapes are still scarce. In this paper, we quantify species-, habitat- and landscape-scale pollen production in the Lublin Upland, SE Poland. The production per unit area was highest (mean = 2.2-2.6 g/m 2 ) in non-forest woody vegetation, field margins and fallows, whilst significantly lower pollen amounts were shown to be available in road verges and railway embankments (mean = 1.3-1.6 g/m 2 ). At landscape scale, natural and semi-natural areas (forests and meadows/pastures) offered ca. 44% of the total pollen resources during the year. Relatively high amounts of pollen (ca. 35% of the year-round total pollen resources) were from winter rape, but this resource was short-term. Man-made, non-cropped habitats added only ca. 18% of the total pollen mass offered for pollinators during flowering season. However, they provided 66-99% of pollen resources available from July to October. There exists an imbalance in the availability of pollen resources throughout the year. Hence, a diversity of natural, semi-natural and man-made, non-cropped areas is required to support the seasonal continuity of pollen resources for pollinators in an agricultural landscape. Efforts should be made to secure habitat heterogeneity to enhance the flower diversity and continual pollen availability for pollinators., Competing Interests: Declaration of competing interest The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper., (Copyright © 2022 The Authors. Published by Elsevier B.V. All rights reserved.)

The scarcity of floral resources and their seasonal discontinuity are considered as major factors for pollinator decline in intensified agricultural landscapes worldwide. The consequences are detrimental for the stability of the environment and ecosystems. Here, we quantified the production of nectar sugars in plant species occurring in man-made, non-cropped areas (non-forest woody vegetation, road verges, railway embankments, field margins, fallow areas) of an agricultural landscape in SE Poland. We also assessed changes in the availability of sugar resources both in space (habitat and landscape scales) and in time (throughout the flowering season), and checked to what extent the sugar demands of honeybees and bumblebees are met at the landscape scale. At landscape-level, 37.6% of the available sugar resources are produced in man-made, non-cropped habitats, while 32.6% and 15.0% of sugars derive from winter rape crops and forest vegetation, respectively. Nectar sugar supplies vary greatly between man-made, non-cropped habitat types/sub-types. These areas are characterized by a high richness of nectar-producing species. However, a predominant role in total sugar resources is ascribable to a few species. Strong fluctuations in nectar resources are recorded throughout the flowering season. March and June are periods with food shortages. Abundant nectar sugars are generally found in April-May, mainly due to the mass flowering of nectar-yielding species in the forests, meadows/pastures and orchards/rapeseed crops. Heterogeneity of man-made, non-cropped habitats is essential to support the supply of July-October nectar sugars for honeybees and bumblebees. Reduced flowering in man-made non-cropped habitats can generate serious food deficiencies, as from summer towards the end of the flowering season >90% of sugars are provided by the flora of these areas. Therefore, highly nectar-yielding plant species that flower during periods of expected food shortages should be a priority for conservation and restoration programs., Competing Interests: Declaration of competing interest The authors declare that they have no known competing financial interests or personal relationships that could have appeared to influence the work reported in this paper., (Copyright © 2021 Elsevier B.V. All rights reserved.)

The dose limit for the skin of the hand is typically converted to a surface of 1 cm 2 , 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 H p (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 H p (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 H p (0.07 slightly exceeded the measured maximum H p (0.07) value. The comparison of measured and simulated dose values showed that the largest differences in H p (0.07) values occurred at the thumb tip, and for ring finger and middle finger of some of the nurses investigated.

Aims: The issue of exposure of eye lenses of employees exposed to ionizing radiation is an interesting topic not only from the point of view of deterministic effects related to the occurrence of cataracts, but also dosimetric aspects, in particular the calibration of detectors in units enabling the assessment of eye lens exposure or personal dose equivalent Hp(3). The paper presents the idea of calibrating thermoluminescent detectors designed for the Hp(3) values measurement of gamma radiation, which the source is the process of annihilation of positrons emitted by the deoxyglucose marker - 18 F radionuclide., Methods: The method was based on the value of air kerma Ka to Hp(3) conversion coefficients (Hp(3,0°)/Ka) developed as part of the ORAMED project. High-sensitivity thermoluminescent detectors (MCP-N) produced in Poland were used in the measurements. During the exposure of the detectors, a 137 Cs gamma radiation source (irradiator 137 Cs/ 60 Co) and a 20cm diameter cylinder filled with water were used., Results & Conclusions: The value of conversion coefficient Hp(3,0°)/Ka for energy 511 keV is 1.31Sv/Gy and the calibration factor is (3.46±0.03)·10 -4 mSv/N (N - number of counts). Verification of the value of the obtained coefficient carried out using a cylinder with a diameter of 20cm showed a difference of less than 2% in relation to the value obtained by the method described in this paper., (Copyright © 2020. Published by Elsevier GmbH.)

A major disadvantage of dose reconstruction by means of thermoluminescence (TL) is the fact that during readout of any TL material exposed to ionizing radiation (i.e., during measuring the glow curve), the radiation-induced signal gets lost. Application of the photo-transferred thermoluminescence phenomenon (PTTL) may offer a solution to this problem. In PTTL, the residual signal that is not destroyed by conventional TL readout (because it comes from deeper electron traps) can be readout through simultaneous stimulation by UV light and heating, allowing to obtain information about the absorbed dose in a second run. The present paper describes the application of PTTL for emergency dose assessment. For this, MTS-N thermoluminescent detectors (LiF: Mg, Ti) were exposed using a high-energy Clinac 2300 medical linear accelerator to doses of 100 mGy, 300 mGy, 500 mGy, 700 mGy and 1000 mGy. Irradiation with UV radiation allowed the determination of the optimal heating time of 3 h, while the optimal temperature was identified to be 70 °C. The results obtained demonstrated the usefulness of the PTTL method for emergency dose assessment. The efficiency of the PTTL method was determined as 19%. Finally it was found that the detector background after UV exposure should not be underestimated during routine dose measurements.

Background: The method of measuring doses based on the thermoluminescence phenomenon is not an absolute method. For this reason, to obtain correct results, it is necessary to calibrate detectors in the known radiation field. This paper presents a method for calibrating thermoluminescent detectors used in the measurement of personal dose equivalents (H p (0.07)) obtained by nuclear medicine facility personnel when handling the 99m Tc radionuclide., Material and Methods: The authors used self-developed high-sensitivity thermoluminescent detectors and a HF320C X-ray unit, as well as a rod phantom. Dosimeters were calibrated in accordance with the ISO 4037-3 standard. During the measurements a vial containing a 99m Tc radionuclide with well-known activity was also used. The energy characteristics were supplemented by using a 137 Cs source (irradiator 60 Co/ 137 Cs)., Results: The value of the calibration coefficient for 118 keV energy energy was (1.90±0.02)×10 -5 mSv/imp. Taking into account the correction factor specified for of 140 keV energy at 0.962, the value of the calibration coefficient for 140 keV energy was determined as (1.83±0.02)×10 -5 mSv/imp., Conclusions: Verification of the calibration coefficient determined for 140 keV energy carried out with a vial containing a 99m Tc radionuclide confirmed the correctness of the procedure. Med Pr. 2019;70(6):669-73., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

The production of 18F-FDG is a multi-stage process, which includes not only obtaining the marker and labelling the radiopharmaceutical but also carrying out the quality control of the obtained compound. The staff can be exposed to ionizing radiation at any stage of production. This article presents the results of hands exposure of staff members employed in a facility, where 18F-FDG is produced and injected into patients. High-sensitivity thermoluminescent detectors (MCP-N) were used for measurements. The measurements were conducted with regard to the occupational structure the employees and the performed procedures. The obtained results showed that the highest risk of radiation exposure for personnel was associated with the quality control of the radiopharmaceutical. The daily doses registered by MCP-N detectors on fingertips reached 4.5 mSv, which may result in exceeding the annual radiation limit of 500 mSv., (© The Author(s) 2018. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.)

Introduction: Obtaining 68 Ga-DOTA-TATE (a radioconjugate consisting of the somatostatin analogue tyrosine-3-octreotate (Tyr3-octreotate or TATE) labelled with the positron emission tomography tracer gallium 68 Ga via the macrocyclic chelating agent dodecanetetraacetic acid (DOTA)) is a complex process and, as with any radiopharmaceutical whose basis is a short-lived radionuclide generator, it is based on a sequence of procedures beginning from the 68 Ge/ 68 Ga generator elution, labelling ligands with a radioisotope, dispensing doses of 68 Ga-DOTA-TATE for patients and finally injection of the preparation to patients. The complexity of this process may contribute to an increased exposure of eye lenses of the staff who perform the above-mentioned procedures, which is especially important at a time when the dose limit on the lens of the eye is being reduced from 150 to 20 mSv yr -1 ., Objective: The work presents the exposure of eye lenses of the personnel of a nuclear medicine department who prepare and inject 68 Ga-DOTA-TATE., Materials and Methods: Radiochemists and nurses were monitored by dosimetry measurements with thermoluminescent detectors (TLDs)., Results: The values of Hp(3)/A-normalised personal eye dose equivalent recorded in the group of radiochemists during the procedure of dispensing the doses of 68 Ga-DOTA-TATE for patients exceeded the value of 274 μSv/GBq., Conclusions: The estimated annual Hp(3) values may exceed 20 mSv, which is particularly important due to the fact that procedures using the 68 Ga radioactivity are only a small part of the daily professional activity of the staff, resulting from the performance of other procedures that require the use of other radioisotopes.

Purpose: Individual dosimetry is undoubtedly one of the best methods of assessing the exposure of personnel to ionizing radiation, however in case of nuclear medicine, the method applied to measure the dose does not always present a picture of the worker's actual exposure. The highly non-homogeneous dose distribution on the hand means that the ring dosimeter, routinely used to measure the Hp(0.07), provides only approximate dose values received by fingertips, the body part most exposed to ionizing radiation. This paper is an attempt to answer the question whether the wrist dosimeter used as a replacement for the ring dosimeter is able to provide information on doses for the most exposed fragments of the hand of an employee during handling procedures with the use of radiopharmaceuticals., Materials: Throughout measurements performed in five nuclear medicine facilities, high-sensitivity thermoluminescent detectors were used., Results: Correction coefficients have been determined, which constitute an amendment to be made to move from the dose recorded by the wrist dosimeter to the doses received by the most exposed hand fragments. The fingertips received on average 25 times higher doses, compared to the values recorded by the wrist dosimeter., Conclusions: A wrist dosimeter can be used to measure the Hp(0.07) in nuclear medicine, including as a gauge of the most exposed parts of the hand - the fingertips. However, the applicability of correction coefficients makes it necessary to ensure a stable position of the wrist dosimeter during routine procedures., (Copyright © 2018 Associazione Italiana di Fisica Medica. Published by Elsevier Ltd. All rights reserved.)

The production of the 18 F isotope-the marker of deoxyglucose ( 18 F-FDG)-the radiopharmaceutical most commonly used in the oncological diagnostic technique of positron emission tomography, requires a cyclotron device. At present, there are nine facilities working in Poland that are equipped with cyclotrons used for producing the short-lived isotopes. The aim of the paper is to determine the hand exposure of workers employed in the two 18 F-FDG production centres taking in to account the production procedures and work system in those facilities. Measurements, which included all professional workers exposed to ionizing radiation that were employed in two facilities, were performed by using high-sensitivity thermoluminescent detectors during the routine activities of the personnel. The work system used at the production centre has an impact on the level of the recorded doses. Among the production procedures performed by the staff, the highest ionizing radiation doses have been received by the staff during the 18 F-FDG quality control. The maximum estimated annual Hp(0.07) for chemists from the quality control department can exceed the annual skin limit dose (500 mSv). The source of lowest doses on the hands are the cyclotron operating procedure and the 18 F-FDG production, provided that these procedures can't be combined with other production procedures.

Background: A radiopharmaceutical is a combination of a non-radioactive compound with a radioactive isotope. Two isotopes: technetium-99m (99mTc) and fluorine-18 (18F) are worth mentioning on the rich list of isotopes which have found numerous medical applications. Their similarity is limited only to the diagnostic area of applicability. The type and the energy of emitted radiation, the half-life and, in particular, the production method demonstrate their diversity. The 99mTc isotope is produced by a short-lived nuclide generator - molybdenum-99 (99Mo)/99mTc, while 18F is resulting from nuclear reaction occurring in a cyclotron. A relatively simple and easy handling of the 99Mo/99mTc generator, compared to the necessary use a cyclotron, seems to favor the principle of optimizing the radiological protection of personnel. The thesis on the effect of automation of both the 18F isotope production and the deoxyglucose labelling process on the optimization of radiological protection of workers compared to manual procedures during handling of radiopharmaceuticals labelled with 99Tc need to be verified., Material and Methods: Measurements of personal dose equivalent Hp(0.07) were made in 5 nuclear medicine departments and 2 radiopharmaceuticals production centers. High-sensitivity thermoluminescent detectors (LiF: Mg, Cu, P - MCP-N) were used to determine the doses., Results: Among the activities performed by employees of both 18F-fluorodeoxyglucose (18F-FDG) production centers and nuclear medicine departments, the manual quality control procedures and labelling of radiopharmaceuticals with 99mTc isotope manifest the greatest contribution to the recorded Hp(0.07)., Conclusions: The simplicity of obtaining the 99mTc isotope as well as the complex, but fully automated production process of the 18F-FDG radiopharmaceutical optimize the radiation protection of workers, excluding manual procedures labelling with 99mTc or quality control of 18F-FDG. Med Pr 2018;69(3):317–327., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

Background: Proper management of bee pastures is considered an important activity for diversity of pollinators and conservation of the population size. In the present study, the floral composition and diversity, flowering spectrum and availability of food resources in natural and man-made habitats in four rural municipalities in Lublin Upland, SE Poland were evaluated. The connection between pollinator-friendly biotopes was also determined and some suggestions are made on creation/supplementation of bee pastures adapted to the arable land structure in eastern Poland (mean acreage 7.65 ha)., Results: Forage species richness (S) differed among vegetation types: the highest S value was found in field margins, while mixed forests represented the lowest species richness (mean ± standard deviation = 37.8 ± 9.5 vs 16.5 ± 2.3). In all habitats, the most abundant flowering was recorded in May. Then the blooming abundance decreased until a complete decline at the end of summer. The mean distance between pollinator-friendly biotopes is 2.4 ± 1.53 km, which is out of the flying range/foraging distance of most pollinators., Conclusion: Shortages of nectar and pollen resources in the agricultural landscape of SE Poland are evident. Therefore it is assumed that the landscape structure requires support in terms of food niches for pollinators and creation/supplementation of bee pastures is necessary, e.g. six to nine patches of 0.025-0.3 ha each within an area of 100 ha. © 2017 Society of Chemical Industry., (© 2017 Society of Chemical Industry.)

Decreasing the individual dose limit of exposure to ionizing radiation to the eye lenses means verifying the need for routine monitoring of the eye lenses of workers exposed to ionizing radiation, including those employed in facilities producing radiopharmaceuticals based on short-lived isotopes. This work analyzes the exposure of the eye lenses of employees of centers that produce the isotopes for positron emission tomography, in particular fluorine-18. It takes into account the employment structure and work system of the discussed centers, including in terms of changing the dose limit of exposure to the eye lenses. This work complements the paper by Wrzesień (2018 Australas. Phys. Eng. Sci. Med. submitted) , which focused on the exposure of workers' hands to ionizing radiation in radiopharmaceutical production centers. Measurements were carried out using high-sensitivity thermoluminescence detectors (LiF: Mg, Cu, P-MCP-N). The measurements covered 17 employees. Our results show that the highest values of personal dose equivalent Hp(3) were recorded for the 18 F-FDG quality control personnel and nurses who injected the radiopharmaceutical in the patients. In the group of nurses, the maximum daily does Hp(3) reached a value close to 200 μSv. For staff who performed the quality control of the 18 F-FDG, the maximum daily dose of Hp(3) exceeded 200 μSv. The estimated annual exposure of the eye lenses of workers in these two occupational groups may exceed the new dose limit (20 mSv/year). Results of this study indicate the need for optimization of the procedures related to quality control of radiopharmaceuticals and the injection of 18 F-FDG in patients.

Background: Thermoluminescent detectors, type MTS-6, containing isotope 6 Li (lithium) are sensitive in the range of thermal neutron energy; the 239 Pu-Be (plutonium-and-beryllium) source emits neutrons in the energy range from 1 to 11 MeV. These seemingly contradictory elements may be combined by using the paraffin moderator, a determined density of thermal neutrons in the paraffin block and a conversion coefficient neutron flux to kerma, not forgetting the simultaneous registration of the photon radiation inseparable from the companion neutron radiation. The main aim of this work is to present the idea of calibration of thermoluminescent detectors that consist of a 6 Li isotope, by using 239 Pu-Be neutron radiation source., Material and Methods: In this work, MTS-6 and MTS-7 thermoluminescent detectors and a plutonium-and-beryllium ( 239 Pu-Be) neutron source were used. Paraffin wax fills the block, acting as a moderator. The calibration idea was based on the determination of dose equivalent rate based on the average kerma rate calculated taking into account the empirically determined function describing the density of thermal neutron flux in the paraffin block and a conversion coefficient neutron flux to kerma., Results: The calculated value of the thermal neutron flux density was 1817.5 neutrons/cm 2 /s and the average value of kerma rate determined on this basis amounted to 244 μGy/h, and the dose equivalent rate 610 μSv/h. The calculated value allowed for the assessment of the length of time of exposure of the detectors directly in the paraffin block., Conclusions: The calibration coefficient for the used batch of detectors is (6.80±0.42)×10 -7 Sv/impulse. Med Pr 2017;68(6):705-710., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

Objectives: Contemporary dental radiology offers a wide spectrum of imaging methods but it also contributes to an increase in the participation of dental radiological diagnosis in the patient's exposure to ionizing radiation. The aim of this study is to determine the absorbed doses of the brain, spinal column, thyroid and eye lens for patients during panoramic radiography, cephalometric radiography and cone beam computed tomography (CBCT)., Material and Methods: The thermoluminescent dosimetry and anthropomorphic phantom was used for measuring the doses. The 15 panoramic, 4 cephalometric and 4 CBCT exposures were performed by placing high-sensitivity thermoluminescent detectors (TLD) in 18 anatomical points of the phantom., Results: The maximum absorbed dose recorded during performed measurements corresponds to the point representing the brainstem and it is 10 mGy. The dose value recorded by the TLD placed in the thyroid during CBCT imaging in relation to the panoramic radiography differs by a factor of 13.5., Conclusions: Cone beam computed tomography, in comparison with panoramic or cephalometric imaging technique, provides higher radiation doses to the patients. Int J Occup Med Environ Health 2017;30(5):705-713., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

Background: The use of X-ray in dental procedures causes exposure of the patient to ionizing radiation. This exposure depends primarily on the parameters used in tooth examination. The aim of the study was to determine the patients exposure and to assess the technical condition of X-ray tubes., Material and Methods: Seventeen hundred dental offices were covered by the questionnaire survey and 740 questionnaires were sent back. Direct measurements were performed in 100 units by using the thermoluminescent detectors and X-ray films., Results: The results showed that the most commonly used exposure time is 0.22±0.16 s. The average entrance dose for the parameters used most commonly by dentists is 1.7±1.4 mGy. The average efficiency of X-ray tube estimated on the basis of exposures is 46.5±23.7 μGy/mAs., Conclusions: The study results indicate that the vast majority of X-ray tubes meet the requirements specified in the binding regulations. Med Pr 2017;67(4):491-496., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

18 F-FDG is the most popular radiopharmaceutical used, among others, in oncological diagnostics by PET technique. The production of 18 F-FDG is a multistep process that begins by obtaining the radioisotope 18 F, and subsequently labelling the radiopharmaceutical, as well as quality control of the resulting compound. In each of these stages, the employee has contact with ionizing radiation. The production of 18 F requires the use of a cyclotron device. Currently in Poland, there are 9 centres equipped with a cyclotron for the production of positron-emitting radioisotopes. The monitoring of the occupational exposure to ionizing radiation in these centres is performed by measuring the effective and equivalent dose. Neither of these forms fully reflects the exposure of the worker, which is largely associated with handling procedures. The 18 F radiopharmaceutical preparation process runs automatically, which partially reduces the level of staff exposure, but the quality control step of the pharmaceutical requires handling procedures with a vial containing an activity of a radiopharmaceutical ranging from 4 GBq to 10 GBq. In the work presented, measurements were performed of hand exposure, in units the equivalent dose (H p (0.07)), of the staff who are involved in the procedures of 18 F-FDG production in one of the national production centres. The high-sensitivity thermoluminescent detectors (MCP) were used to measure the doses. The measurements were performed for three groups of workers: operators of the cyclotron, those who produce the 18 F-FDG, and quality control staff. Detectors were placed on the fingertips of the left and right hand, as well as in a standard ring dosemeter location. The results indicate that the largest exposure happens among the group of workers involved in the radiopharmaceutical's quality control. The doses recorded by the MCP detectors placed on the fingertips during one working day reach a value up to 2 mSv, which may result in exceeding the annual dose limit (500 mSv).

The main aim of this study was to highlight the problems of personnel exposure when administering (153)Sm-labelled ethylene diamine tetramethylene phosphonate-Quadramet(®) to patients and especially to evaluate hand exposure of the personnel. The exposure levels of patients' families and the people who takes care of the patients treated by Quadramet(®) were also estimated. Thermoluminescent detectors were used to measure the doses. The doses received during the injection of the Quadramet(®) by the nursing staff have been determined at the level of 1/150 dose limit for the skin. Exposure of members of the patient's family staying 1.5 m away from the patient being treated with Quadramet(®) has been estimated to be 0.40 mGy., (© The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.)

Positron emission tomography (PET) is now one of the most important methods in the diagnosis of cancer diseases. Due to the rapid growth of PET/CT centres in Poland in less than a decade, radiation protection and, consequently, the assessment of worker exposure to ionising radiation, emitted mainly by the isotope (18)F, have become essential issues. The main aim of the study was to analyse the doses received by workers employed in the Medical Diagnostic Centre. The analysis comprises a physicist, three nurses, three physicians, three technicians, as well as two administrative staff employees. High-sensitivity thermoluminescent detectors (TLDs) were used to measure the doses for medical staff. The personnel was classified into categories, among them employees having direct contact with the 'source of radiation'-(18)FDG. The TLDs were placed on the fingertips of both hands and they were also attached at the level of eye lenses, thyroid and gonads depending on the assigned category. The highest dose of radiation was observed during the administration of the (18)FDG to the patients. In the case of the physicist, the highest dose was recorded during preparation of the radiopharmaceutical-(18)FDG. The body parts most exposed to ionizing radiation are the fingertips of the thumb, index and middle finger.

Background: There are about 200 underground tourist routes in Poland. There are caves, mines or underground structures. This paper presents the results of the research intended to identify the extent of the occurrence of radon concentrations in underground areas of tourist routes., Material and Methods: We conducted the measurement of periodic concentrations of radon (1-2 months) in the summer using type Tastrak trace detectors. We determined the average concentrations of radon in air in 66 underground tourist routes in Poland., Results: The research results comprise 259 determinations of average radon concentrations in 66 routes. The arithmetic average of the results was 1610 Bqm-3, and the maximum measured concentration was over 20,000 Bqm-3. The minimum concentration was 100 Bqm-3 (threshold method) considering the arithmetic average of the measurements. It was found that in 67% of the routes, the average concentration of radon has exceeded 300 Bqm-3 and in 22 underground routes it exceeded 1000 Bqm-3., Conclusions: Radon which occurs in many Polish underground tourist routes may be an organizational, legal and health problem. It is necessary to develop a program of measures to reduce radon concentrations in underground routes, especially routes located in the former mines., (This work is available in Open Access model and licensed under a CC BY-NC 3.0 PL license.)

Background: Transcriptional regulation in multi-cellular organisms is a complex process involving multiple modular regulatory elements for each gene. Building whole-genome models of transcriptional networks requires mapping all relevant enhancers and then linking them to target genes. Previous methods of enhancer identification based either on sequence information or on epigenetic marks have different limitations stemming from incompleteness of each of these datasets taken separately., Results: In this work we present a new approach for discovery of regulatory elements based on the combination of sequence motifs and epigenetic marks measured with ChIP-Seq. Our method uses supervised learning approaches to train a model describing the dependence of enhancer activity on sequence features and histone marks. Our results indicate that using combination of features provides superior results to previous approaches based on either one of the datasets. While histone modifications remain the dominant feature for accurate predictions, the models based on sequence motifs have advantages in their general applicability to different tissues. Additionally, we assess the relevance of different sequence motifs in prediction accuracy showing that even tissue-specific enhancer activity depends on multiple motifs., Conclusions: Based on our results, we conclude that it is worthwhile to include sequence motif data into computational approaches to active enhancer prediction and also that classifiers trained on a specific set of enhancers can generalize with significant accuracy beyond the training set.

The specific nature of work in nuclear medicine departments involves the use of isotopes and handling procedures, which contribute to the considerable value of an equivalent dose received, in particular, by the fingertips. Standard nuclear medicine department uses ring dosemeters placed usually at the base of the middle finger. The main aim of the study was to find out whether a relationship exists between the doses recorded by thermoluminescent detectors placed at various locations on the radiopharmacists' hands and the doses recorded by the ring detectors, and to determine the character of that relationship. The correction factor represents a correction value to be used to calculate the doses which might be received by locations on the hand from the dose recorded by the ring dosemeter. The dose recorded by the ring dosemeter is on the average five times lower than that received by the fingertips of thumb, index and middle fingers.

Background and Objectives: The goal of this study was to measure absorbed doses of radiation to the hands of medical staff performing sentinel node biopsy (SNB) in skin melanoma patients., Methods: The study was conducted from January 2004 to May 2004, during SNBs (lymphoscintigraphy-(99m)Tc on albumin carrier, surgery after 24 hr; blue dye; intraoperative detection of gamma radiation) in 22 skin melanoma patients. During lymphoscintigraphy and surgical procedures, 57 highly sensitive thermoluminescent dosimeters (TLDs) were placed on different parts of the hands of the medical staff., Results: Mean doses of radiation recorded on different parts of the hands of the physician injecting the radiotracer ranged from 2.43 to 84.11 microSv for single procedures, ranged from 3.20 to 5.84 microSv for the hands of surgeon, and ranged from 2.65 to 5.47 microSv for the hands of the remaining members of the medical staff. Absorbed doses of radiation to the hands of helping medical staff present in operating room was only slightly lower than absorbed doses to the hands of operating surgeon and assistant surgeon., Conclusion: The maximum recorded dose during this study was 1,900 times smaller than the current 1-year dose limit recommended by the International Commission on Radiological Protection (ICRP)., ((c) 2006 Wiley-Liss, Inc.)