Annual Radiation Dose Research Articles

Martian Residents: Mass Media and Ramsar High Background Radiation Areas.

Considering current controversies regarding the health effects of low doses of ionizing radiation, study of the high background radiation areas such as Ramsar, Iran can help scientists better evaluate the validity of linear no-threshold (LNT) hypothesis. Ramsar is a coastal city in northern Iran with some areas known to have the highest levels of natural background radiation in the world. The mean annual dose of the residents of high background radiation areas (HBRAs) of Ramsar is 10 times higher than the public dose limit recommended by the ICRP (1 mSv/year) and a proportion of the residents receive annual doses as large as 260 mSv (13 times higher than the occupational dose limit recommended by the ICRP). A report published in Popular Science proclaims that background radiation in Ramsar approaches that of the Martian surface. However, estimates show that the maximum annual radiation dose in HBRAs of Ramsar can be much higher than that of the Martian surface (260 mGy/y vs 76 mGy/y). Furthermore, a Guardian report introduces Talesh Mahalleh, a district in Ramsar, as an inhabited area with the highest levels of natural radioactivity in the world and C Net claims that the best Mars colonists may come from places like Iran and Brazil. In spite of current concerns, nearly all residents still live in their paternal dwellings and there are not consistent reports on any detrimental effects. It is worth noting that, due to small sample size, to draw a firm conclusion about the health effects of high level natural radiation in Ramsar, in particular about the cancer risk, current information is not sufficient and further studies are needed.

Assessment of orthopedist exposure to occupational doses of radiation in foot and ankle surgeries

Objective: To measure the doses of occupational radiation to which a physician who performs orthopedic surgery of the foot and ankle using a fluoroscopy device is exposed during work and to compare those doses with the values provided in the current legislation and propose measures of radioprotection. Methods: Thermoluminescent dosimetry (TLD) was used to measure radiation in critical target areas (whole-body, lens, thyroid, right and left hands) of the surgeon’s body during all the surgical procedures performed by him between 12/19/2017 and 2/5/2018. From the mean dose values obtained for the procedures, the dose of annual radiation exposure was estimated for each of the regions analyzed and compared with the current legislation. Results: The estimate of the annual radiation dose received by the surgeon to the chest region, above the lead apron, was 5 times higher than that established by the national legislation. However, considering the use of the lead apron, the dose was acceptable. Estimates of equivalent doses for the limbs and thyroid had results within the levels required by the current legislation. The equivalent dose for the lens, on the other hand, was 4 times higher than that established by the legislation. Conclusion: During the workday, the foot and ankle orthopedic surgeon is exposed to doses of radiation higher than those considered acceptable. The data corroborate the need to wear radiological protective clothing, especially a lead apron and goggles. Level of Evidence IV; Prognostic Study; Case Series.

Impressive Radiation Stability of Organic Solar Cells Based on Fullerene Derivatives and Carbazole-Containing Conjugated Polymers.

We explored the radiation stability of carbazole-based electron-donor conjugated polymers, acceptor fullerene derivative [60]PCBM, and their blends as active layer components of organic solar cells. An exposure toγ rays induced evident degradation effects in bulk samples of the pristine fullerene acceptor ([60]PCBM) and two investigated electron-donor conjugated polymers: PCDTBT and PCDTTBTBTT. The most severe radiation damage occurred in [60]PCBM as can be concluded from the significant losses in open circuit voltage, fill factor, and efficiency of photovoltaic (PV) devices comprising the exposed fullerene acceptor. Conjugated polymers PCDTBT and PCDTTBTBTT showed substantially different radiation stabilities: the samples of PCDTTBTBTT exposed to 200 Gy lost ∼25% of their nominal photovoltaic efficiency due to a substantial decay of all device parameters, while PCDTBT alone showed just a minor aging under the same conditions. The fullerene-polymer composites were much more resistant with respect to the radiation damage than the bulk samples of pristine materials. In particular, the PCDTBT/[60]PCBM composite films demonstrated an outstanding radiation stability while maintaining more than 80% of the initial photovoltaic efficiency after exposure to γ rays with a maximum absorbed dose of 6500 Gy. Considering an average annual radiation dose of 160 Gy according to the NASA estimations for satellites at geocentric Earth orbits, organic solar cells based on PCDTBT/[60]PCBM blends hold apromise to deliver lifetimes well above 10 years. The revealed impressive radiation stability of PCDTBT/[60]PCBM blends in combination with other advantages of organic solar cells, for example, their mechanical flexibility and lightweight, points to a bright future of this PV technology in space industry applications.

220Rn (Thoron) Geohazard in Room Air of Earthen Dwellings in Vietnam

Thoron’s (220Rn) contribution to α-radiation exposure is usually considered negligible compared to that of 222Rn (radon). Despite its short half-life of 55.6 seconds, thoron can be exhaled from porous surface layers of building materials into indoor air where people subsequently inhale radioisotopes, including metallic radioactive progeny. Bare surfaces of dry porous soil with relatively high 232Th content can pose a thoron radiation hazard in indoor air. On northern Vietnam’s Đồng Văn karst plateau, the spatial distribution of thoron was determined in indoor air of traditional earthen and other types of dwellings using portable RAD7 and SARAD® RTM 2200 detectors. “Mud houses” are constructed with local compacted soil and typically do not have any floor or wall coverings (i.e., no plaster, wallpaper, or paint). Detailed measurements in a mud house revealed levels of thoron in room air averaging >500 Bq m-3. The spatial distribution of α-radiation from thoron in indoor air at a distance of about 1 m from interior walls was fairly homogeneous and averaged ~200 Bq m-3. Most concerning, from a human health perspective, were the high thoron concentrations of up to 884 Bq m-3 in sleeping areas near mud walls. The average annual thoron radiation dose to inhabitants of mud houses was estimated based on 13 hours of daily occupancy, including daily activities and sleeping. The estimated average thoron inhalation dose of 27.1 mSv a-1 during sleeping hours near mud surfaces accounts for nearly 75% of the total estimated radon and thoron inhalation dose of 37.4 mSv a-1 from indoor mud house air. Our conservative annual radiation dose estimates do not include subsequent radiation from inhaled metallic progeny of thoron. Our data demonstrate a significant human health risk from radiation exposure and a critical need for remediation in traditional northern Vietnamese mud house dwellings.

Proposed use of in vivo x-ray fluorescence to investigate health impact of Gd in MRI contrast agents and Sr in diet

Introduction: In vivo x-ray fluorescence (XRF), along with in vivo neutron activation can be used to measure elemental content in living human subjects. Two examples of current interest will be presented. Gadolinium based contrast agents (GBCA) are widely used, because they greatly facilitate magnetic resonance imaging studies. Initially considered completely benign, it was found that these GBCAs could be damaging to people with compromised kidney function. More recently concern has been raised about possible impact on people with normal kidney function. We have been developing an xrf method to measure Gd in bone. Strontium is harmful to bone in excess. However, Sr supplement administered to people diagnosed with osteoporosis reduced fracture risk. Because there were cardiovascular side effects, this treatment has been withdrawn. Risk of hip fracture varies from country to country. It is highest in North America and two times lower in East Asian countries. We developed an xrf method to measure Sr in bone. In an early study of a convenience sample of Canadian residents, we found that people of East Asian origin had three times the level of Sr in bone as people of Caucasian origin. This gives rise to an hypothesis that modest levels of Sr, perhaps acquired through lifelong diet, could reduce the risk of osteoporosis. Materials and methods: Xrf requires a source of x-rays or (-rays, which can then excite x-rays that are characteristic of a particular element in a sample. A detector is placed to collect the scattered x-rays and (-rays from the sample. For Gd measurement, we use 88keV (-rays from a 109Cd source and an array of four hyperpure germanium detectors. For Sr we use x-rays and (-rays from a 125I source, with energies between 22 and 35keV. We use a Si(Li) detector. The effective radiation dose in each of these measurements is less than 1:Sv. This compares, for example to annual background radiation dose of ∼1600:Sv in Lisbon. Results: We measured Gd in tibia of 11 people who had previously received GBCA and 11 control subjects [1]. As a group, the exposed subjects had significantly higher bone Gd than the controls, although the difference was small. We made repeated measurements of bone Sr in ten female volunteers who had chosen to take Sr supplements [2]. Over periods of up to four years, their bone Sr increased dramatically. The increase varied from a factor of ten to a factor of one hundred between subjects. Discussion and conclusions: We should like to improve the precision of the bone Gd measurement. However, the present system is sufficient to begin to investigate retention and storage of Gd for different GBCAs and in different types of subjects. The dramatic increase in bone Sr following supplementation raises the possibility that providing Sr to people already suffering from osteoporosis is too much, too quickly, too late and that a lifelong dietary adjustment might be a healthier option.

On uranium 234U and 238U radionuclides in calcium and magnesium supplements and the potential effective radiation dose assessment to the consumers

ABSTRACTIn this survey the concentrations of the radioactive nuclides uranium 234U and 238U were determined in the most popular calcium and magnesium supplements for adults in Poland. It was also investigated whether the supplements contain uranium isotopes and could be a potential source in the human diet and have an influence on the value of effective radiation doses to the consumers. The analyzed calcium and magnesium pharmaceuticals contained organic or inorganic compounds, several of natural origin as mussel’s shells, fish extracts, or sedimentary rocks. As results showed, 234U and 238U concentrations in natural origin calcium and magnesium supplements were significantly higher than in other, synthetic ones. The highest 234U and 238U activity concentrations were determined in tablets from mussel’s shells. The radiochemical hazard was assessed and the highest annual radiation dose was found in 234U and 238U present in supplements produced from shells or dolomite rock.

Determination of natural uranium by various analytical techniques in soils of Zacatecas State (Mexico)

238U is a radionuclide present in the earth’s crust that provides 65.9% of annual average radiation dose and represents 99.27% of total uranium. 238U has been determined in samples from undisturbed topsoil in the Zacatecas State, Mexico, using several analytical techniques. ICP-MS and α-spectrometry produced the most reliable results. Uranium concentrations found in topsoil samples (0.4–3.7 mg kg−1) were similar to its average crustal abundance (2.8 mg kg−1) and indicate high homogeneity without evidence of enrichment. The average concentration of 2.1 mg kg−1 can be established as uranium background level in the topsoil of Zacatecas (Mexico).

A Phantom Menace to Medical Personnel During Endovascular Treatment of Cerebral Aneurysms: Real-Time Measurement of Radiation Exposure During Procedures

The number of endovascular treatment procedures performed for cerebral aneurysms has markedly increased. However, little is known about the annual effective radiation dose to medical staff in neurointervention fields. We performed a retrospective observational study to investigate the real-time radiation dose to surgeons, nurses, anesthesiologists, and radiologic technologists during endovascular treatment of intracranial aneurysms. We measured the real-time radiation doses for 2 weeks using standard and reinforced protection, during which 28 procedures were performed, including 23 coil embolizations for unruptured intracranial aneurysms. Four procedures were excluded because of an inadequately equipped sensor, which resulted in inappropriate data collection. The procedure time was defined from intubation to extubation. Five RaySafe i2 detectors were installed at the chest level of the operator, attending nurse, radiologic technologist, and anesthesiologist and just inside the front door of the hybrid operating room. The median doses per session with standard protection to the operator, attending nurse, anesthesiologist, and radiologic technologist were 11.16, 2.60, 4.76, and 1.93 μSv, respectively. The dose to the operator, attending nurse, and anesthesiologist had decreased to 6.63, 0.39, and 1.52 μSv under reinforced protection, respectively. However, the session dose for the radiologic technologist had increased to 3.12 μSv. We confirmed the differences in the amount of radiation exposure for different roles. An additional lead screen, which provided more effective protection on the operator side, was proved effective for attenuating radiation exposure during endovascular treatment. All personnel involved in the hybrid operating room were exposed to acceptable effective doses.

Radiation protection of melting of radioactive contaminated metal

An integral component of modern technogenic activities using nuclear energy is the accumulation of radioactively contaminated metals. Solving the issues of recycling or returning these metals to reuse is inextricably linked to ensuring the radiation safety of people and the environment at all stages of the technological cycle using radioactive metal. Possible consequences of the effect of ionizing radiation on the human body are considered, the features of radioactively contaminated metal as a possible source of radiation for production personnel are investigated, as well as the analysis of radiation safety of the utilization of radioactively contaminated metal by its melting using self-deactivation effect. It is noted that an important element of the complex of measures for radiation safety of production personnel is the assessment of the radiation situation, and its main purpose and overall content is indicated. The basic principles of radiation safety are formulated. The choice of rational options for the actions of production personnel in the disposal of radioactive contaminated metal eliminates the exposure of people to radiation levels that exceed standard values. Additional radiation exposure to the environment is also excluded. It is shown that the criterion of radiation safety of a metal is the maximum dose rate of gamma radiation from its surface, which ensures that the limit of the individual annual effective radiation dose is not exceeded. It is reasonable to review the permissible levels of radiation exposure of personnel performing operations with radioactively contaminated metal in accordance with the procedure established by the Ministry of Health of Ukraine. A multistage system for cleaning ventilation emissions from a melting furnace using an electrostatic filter at the last stage, which directly cleans gas aerosol emissions from radionuclides, is proposed. The results of the study can contribute to the return to production of large volumes of radioactively contaminated metal, significantly improve the technical and economic performance of metal production and help to prevent environmental disturbances.

Historical perspective on the department of energy mortality studies: focus on the collection and storage of individual worker data

Purpose To present how the Department of Energy’s (DOE) Comprehensive Epidemiologic Data Resource (CEDR) is integrated into the Million Person Study of Low Dose Health Effects (MPS). The history of DOE’s worker health surveillance and its epidemiology program are described. Methods and materials A standard protocol is used to extract data from CEDR for use in the MPS. The data files are pulled from CEDR to form the basis for the cohort analyzed in the MPS. The previous study data are reviewed to formulate the protocol for the MPS study cohort. The activities needed to update the data to construct the new analytic files are carried out in parallel. The primary efforts relate to updating the vital status, retrieving cause of death information and calculating annual radiation doses for the specific organs of interest. Working data files containing the updated data are produced for construction of analytic data files used in the biostatistical analysis. At study completion the working and analytic data files are placed into CEDR for use by other researchers. Results The use of CEDR to study the scientific and maintenance workers at the Los Alamos National Laboratory which is currently underway is used to demonstrate the process. Conclusions There is a pressing need to answer the question of the health risk of exposure to chronic low-level exposure to ionizing radiation. Using CEDR as the starting point to identify new cohorts to include in the MPS is a cost-effective and a time efficient way to expedite answering this question.

Development of measures to protect the population and prevent pollution based on the study of the radiation background of the object

In the modern world, the energy of the atom is used in industry, medicine and other spheres of human activity. However, the usage of radioactive substances can have a negative impact on the environment, the health of workers and the public. Therefore, it is important to keep a close watch on the radiation situation in the immediate vicinity of facilities where radioactive substances are used or stored. These can be nuclear power plants and industrial enterprises, as well as areas with a naturally elevated background radiation level. In this paper, a study of the background radiation of the object of possible radioactive contamination – Gatchina Palace in Gatchina, Leningrad region was carried out. On the basis of measurements made, we have performed the calculation of the annual radiation doses of staff and tourists, as well as issued recommendations to ensure the radiation safety of employees and visitors of the Gatchina Palace.

PROBLEMS OF RADIO SAFETY OF THE POPULATION OF THE ZAPORIZHZHIA REGION WHICH RELATES TO EXPOSURE TO BASIC SOURCES (by review of the literature).

The analysis of scientific literature is carried out in order to generalize the data of many years of research on radioe- cology of the environment of the population of the Zaporizhzhia region. The results of researches on the main sources of radioactive contamination of the territory, levels and structure of radiation doses of the population due to the natural radiation, diet, medical procedures, and the dose burden of the population are estimated. The main sources of radiation sources existing in the Zaporizhzhia region are considered, their characteristics are given, the rate of their influence on the environment and human is given. For this purpose a wide range of official literary sources and own researches were used.The Zaporizhzhia region is located in the south-eastern part of Ukraine and remarcable of the geomorphological structure, which is characterized by the presence of Ukrainian crystalline array enriched with minerals with an ele- vated level of natural radioactivity. This explains the large component of the radiation dose of the population due to the natural component. Total medieval efficiency of the population dosage of the Zaporizhzhia region at the expense of the natural component - 4,37 mSv, the main contribution to this dose is Radon-222 - 76 %. The level of radon-222 in the air of residential premises ranges from 37 to 112 Bq·m-3. Moreover, the percentage of exceeding the norm (100 Bq·m-3) is from 8% to 62%, depending on the administrative district. On average, 25 % of residential buildings in the region do not match the requirements of NRSU-97 regarding the content of radon in the air of the premises. Even more acute problem of the increased Radon radiation appears for the children's population. Due to the more stringent requirements of NRSU-97 regarding Radon content in the air of premises of preschool education- al institutions (PEI) (50 Bq·m-3), 99% of the premises of the PEI do not match the standards. Doses of children radi- ation because of Radon are higher than in adults and amounted to an average of 6.4 mSv per year with a spread of 4.3-9.7 mSv.The second place after Radon exposure to Zaporozhia region is a medical exposure. The analysis of patient dose loads in recent years suggests that the annual dose of irradiation of the population fluctuates in the range of 0.86-0.97 mSv·year-1, the average dose of irradiation is 0.9 mSv·year-1, which is almost 50 % more than the average Ukrainian rate and exceeds the average in the world twice.In the Zaporizhzhia region, the total annual radiation dose of the population due to the main sources of radiation is 5.0 mSv·year-1, with the main contribution of Radon-222 - 3.3 mSv and medical exposure - 0.9 mSv. Radon-222 in the air of the premises is the most important radiation factor for the population of Zaporizhzhia region, which creates an average risk level that is unacceptable for the population and requires careful regulatory control with the help of governmental and regional programs.

Investigation the building walling influence on the radon concentration distribution in the soil

Radon and its progeny in the indoor air form more than 70 % of the annual individual radiation dose for a modern human; they are the second leading cause of lung cancer after smoking. Under such conditions ensuring of the buildings radon safety is an extremely important scientific and practical problem, which is especially relevant for projected constructions. In this case mathematical simulation is the only way to predict radon levels in the future. Soil under the building is the main source of radon entry in indoor air, therefore radon safety of building project is determined by the construction and condition of its underground walling. The article deals with the influence of the building structural features on the amount of radon load on underground walling as one of the main factors of the formation of the radon conditions in the building. Two-dimensional stationary model of diffusion radon transport in the system «soil-atmosphere-building» is used for the calculation of radon concentration fields in the soil air of the base of the building. The obtained fields of radon concentration in the soil air give an opportunity to estimate the changes in the radon field in the neighbourhood of the building.

300. Computed tomography use in a large italian region: Trend analysis 2004–2014 of emergency and outpatient CT examinations in children and adults

Purpose To analyse Computed Tomography (CT) use in recent years in a high population density area in Italy (approximately 10 million inhabitants, including 1 million children), focusing on the developing age. Methods and materials Retrospective analysis of records from the Health Care IT System, covering more than 400 hospitals and clinics. Description of CT use between 2004 and 2014 in emergency and outpatient care and assessment of the radiation exposure trend. Results Over 9 million scans were performed. Emergency procedures showed a global increase of 230%, which mainly consisted of Head exams. In the global outpatient setting, the annual number of CT scans per person increased approximately 19%. A moderate increase in CT exams was observed in the developing age population, while a remarkable increase in Dental, Chest and Abdominal procedures occurred within the 10–30-year age range. The increase in the mean annual dose per caput in the global patient pool was approximately 42%, increasing from 0.72 mSv to 1.03 mSv. The population rate that received an annual radiation dose per caput from CT higher than 1 mSv tripled in the 11-year interval, increasing from 16 to 48%. Conclusion The outcomes raise a special concern for teenagers and young adults, taking into account that the widespread use of CT represents probably the single most important achievement in diagnostic radiology. The increase in CT use and in the CT-derived radiation dose in the population is occurring in spite of the evidence of the substantially improved carcinogenic potential of low doses of X-ray radiation, particularly for children. In contrast with several published investigations, which underline the radiation risk for paediatric age, the level of detail of the data processed in this study highlights a remarkable increase in the irradiation of teenagers and young adults, whose risk tends to be underestimated.

Evaluation of Occupational Radiation Dose in One Year for Operators Working in CT Scan Centers

Introduction: Becuase of the most radiation dose receiving by human is related to medical radiation exposures, and also Computed Tomography (CT) is a special type of radiography that is one of the main method of radiation exposure today, and it's growing increasingly. Therefore, radio technologists working in CT scan imaging centers, are at risk of radiation. Due to the high amount of radiation factors (like kilo-voltage) in CT scans, we evaluated the annual radiation dose of operators working in CT scan imaging centers in this study. Materials and Methods: In this study, the radiation dose of 30 operators has been calculated by using tow Thermoluminescence Dosimeter (TLD) for each one. All of operators were working in CT scan imaging centers or hospitas in Tehran. They used TLDs on their medical cover for 3 months. This protocol was repeated 2 times to ensure repeatability. Also the type and number of CT scans that each person has done was recorded. Results: The recieved dose by TLD was estimated to range from 0.06 to 0.13 mGy (milliGray) in two 3-month periods. Accordingly, the annual dose was estimated to be between 0.12 and 0.26 mGy with mathematical calculations. Conclusion: The occupational radiation dose for operators working in CT scan centers is as low as background radiation in one year. Also It is much lower than the annual limited dose approved by radiation protection organization. So the result of this study showed a proper protection of radio-technologists in CT scan centers.

Coronary Calcium Burden in Breast Cancer Patients Receiving Adjuvant Radiation Therapy

Coronary artery calcium (CAC) score had been reported as an important imaging predictor for coronary artery disease (CAD). Even today, tangential radiotherapy (RT) in left-sided breast cancer (BC) still harbored potential harm to the heart, especially to the left anterior descending coronary artery. Previous studies took the mean heart dose as a surrogate of RT-associated cardiac toxicity, but no data were available on the radiation dose of each coronary artery. We aimed to explore the relation of CAC score and coronary radiation doses in BC patients treated with adjuvant RT. Additionally, we would like to examine the impact of other risk factors of CAD on the increment of coronary calcium burden. We retrospectively reviewed 146 BC female patients (median age at RT 50.5 years [range 24–82], median follow-up time 6.3 years [range 0.3–10.7]), treated with complete course of adjuvant RT in our institution from 2002 to 2010. All patients had received tangent field RT of 50 Gy at least to the breast or chest wall. We retrieved the following data by reviewing medical records: age, risk factors of CAD (diabetes, hypertension, hyperlipidemia, body mass index≧25), and treatment-related profiles. Pre-RT and post-RT computed tomography (CT) scans were obtained, and all CT scans were evaluated by an experienced cardiovascular radiologist in determining the absolute CAC scores of the left main artery (LM), left anterior descending coronary artery (LAD), left circumflex artery (LCX), and right coronary artery (RCA). The annual increment of CAC (CACinc) was calculated by dividing the difference of pre-RT and post-RT absolute CAC score by the time interval between two CT scans (in years). Since CT dose planning was introduced from August 2006 onwards in our institution, dosimetric data were available in 114 patients only. The contouring of each coronary artery was cooperated by two experienced cardiovascular radiologist and radiation oncologist. For left-sided BC, the mean dose and maximal dose of LAD were 1923.60 ± 906.65 cGy and 5155.59 ± 365.49 cGy (mean ± SD), respectively. The radiation doses of LAD and LCX were significantly higher in left-sided BC than those of right-sided BC (p <0.0001). However, there was no correlation between annual CACinc values and coronary radiation doses. The annual CACinc values of LAD, LCX and RCA were not significantly different in left-sided versus right-sided BC. Adjuvant chemotherapy with anthracycline- or taxane-containing regimens showed a trend of significant association with annual CACinc of LAD (p = 0.07). BC patients carrying two or more risk factors of CAD had higher annual CACinc values of LAD (p = 0.04). Our results do not support radiation-induced accelerated coronary calcium burden in BC patients treated with adjuvant RT. For BC patients undergoing adjuvant chemotherapy or carrying two or more risk factors of CAD, intensive follow of CAC increment by CT imaging may be important for early prediction of future CAD episode.

On the extraction efficiency of highly radiotoxic 210Po in Polish herbal teas and possible related dose assessment

Presented are results of a study on 210Po extraction efficiency in Polish herbal teas and risk to the human consumer due to exposure from highly radiotoxic, carcinogenic decay particles emitted by 210Po. 12 most popular commercially available Polish herbal teas, as well as their infusions in tap and filtered water, were analyzed and 210Po activity concentrations were calculated. The results of 210Po activity determination in dried plants were from 2.11 ± 0.09 for milk thistle to 33.7 ± 0.4 Bq·kg−1 dry wt. for cistus what equaled 4.21 ± 0.18 for milk thistle and 43.8 ± 0.5 mBq per one teabag. The extraction efficiencies into tap water ranged from 4.93 ± 0.39 for lime to 27.4 ± 1.4% for elderberry, while for filtered water were between 7.55 ± 0.47 for lime and 20.3 ± 1.1% for elderberry. There were no statistically significant differences between both extractions and no correlation between 210Po extraction efficiency and 210Po activity in dried herbs. The studies indicated the analyzed herbal teas consumption should not contribute significantly to the annual effective radiation dose in Poland.

210Po and 210Pb in forest mushrooms of genus Leccinum and topsoil from northern Poland and its contribution to the radiation dose

Wild growing mushrooms are traditional food items for man and also an important source of nutrients for small and big wildlife. Nevertheless, they can be species - specifically vulnerable for contamination with heavy metals and radionuclides. We studied a less known phenomenon of accumulation of highly toxic, the alpha-radiation emitter such as 210Po and the beta emitter 210Pb by three Leccinum mushrooms: orange oak bolete L. aurantiacum (Bull.) Gray (previous name Leccinum aurantiacum var. quercinum Pilát), foxy bolete L. vulpinum Watling and slate bolete L. duriusculum (Schulzer ex Kalchbr.) Singer. Fungal and soil materials were collected from areas of a different geochemical composition in the northern regions of Poland. In parallel evaluated was the risk to human consumer due to possible intake of 210Po and 210Pb with a mushroom meal. Results showed a heterogeneous distribution of 210Po and 210Pb activity concentrations within caps and stipes of fruiting bodies. Overall activity concentration for whole dried fungi material ranged from 0.59 ± 0.38 to 3.2 ± 0.2 Bq 210Po kg−1 and from 0.45 ± 0.04 to 3.1 ± 0.2 Bq 210Pb kg−1. Evaluation showed that Leccinum mushrooms consumed by locals in typical quantity of 0.5 kg (dry biomass) can contribute into annual effective radiation dose at 0.90–3.81 μSv from 210Po decay and 0.31–2.14 μSv from 210Pb decay, which is a small portion of the annual effective radiation dose of 210Po and 210Pb for human inhabiting the northern regions of Poland.

Utilizing Monte Carlo Computations to Estimate Radiation Doses From Some Cosmetics.

Monte Carlo simulations are exploited to assess the annual radiation doses from some cosmetics due to the radioactive decay series of U and Th and to the radionuclide K. The measured radioactivity concentrations are entered into simulation codes modeled and implemented by Monte Carlo n-particle software. The concentrations are found to be relatively high for a large number of the samples. The Monte Carlo-simulated gamma-radiation annual doses are compared with the results of another theoretical approach. Both methods are in good agreement with each other and predict low doses from use of cosmetics.

Radiation protection measures: Implications on the design of neurosurgery operating rooms

ObjectiveTo describe pros and cons of some radiation protection measures and the implications on the design of a neurosurgery operating room. Material and methodsConcurring with the acquisition and use of an O-arm device, a structural remodelling of our neurosurgery operating room was carried out. The theatre was enlarged, the shielding was reinforced and a foldable leaded screen was installed inside the operating room. Radiation doses were measured in front of and behind the screen. ResultsThe screen provides whole-body radiation protection for all the personnel inside the theatre (effective dose <5μSv at 2.5m from the gantry per O-arm exploration; 0.0μSv received behind the screen per O-arm exploration; and undetectable cumulative annual radiation dose behind the screen), obviates the need for leaded aprons and personal dosimeters, and minimises the circulation of personnel. Enlarging the size of the operating room allows storing the equipment inside and minimises the risk of collision and contamination. Rectangular rooms provide greater distance from the source of radiation. ConclusionFloor, ceiling and walls shielding, a rectangular-shaped and large enough theatre, the presence of a foldable leaded screen, and the security systems precluding an unexpected irruption into the operating room during irradiation are relevant issues to consider when designing a neurosurgery operating theatre.