Radiation Monitoring Research Papers - Academia.edu (original) (raw)

2025, PubMed

Fora measurementto be usefulas a screeningtest, it should accurately reflect risk (offracture). True prospective evalua tion of risk by accepted epidemiologic methods is wholly dependent upon fracture incidence data (1). To our knowl edge, there is no published data which prospectively relates BMC to purely fracture incidence, and OHTA also indicates that they havenot receivedsuchdata. (It shouldbe notedthat previous comparisons of BMC for â€oefracture casesâ€• compared with â€oenormalsâ€• do not recognize that BMC, like blood pres sure, is a continuum; in addition, age-related BMC does not define â€oenormal.'@) However, in October, 1984, we presented at the Western Regional Meetingof the SNM in Monterey,California data relating BMC measurements at four different skeletal sites to prospective fracture incidence (2). The good news is that we were able to predict future fracture risk from BMC measure ments, and this is the essentialmessage which OHTA needs to receive. However, our data indicates that the strongest deter minant of successful risk prediction is the skeletal site, and not the specific technique used to measure BMC at that site. We have found that all four of our measurement sites (spine, Os calcis, distal radius, proximal radius) predict risk to some degree, but that the os calcis does it best. Thus, there is not good rationale for pitting dual-against single-photon absorptiometry. Once we know which skeletal site is most useful for screening (risk prediction), the next question is which technique is necessary to measure that site accurately. Of course, it is necessary to use dual photon technology for the spine, but it has no advantage over single

2025

The effort to estimate the radiation dose received by an occupationally exposed worker is a complex task. Regulatory guidance assumes that the stochastic risks from uniform and non-uniform whole-body irradiations are equal. An ideal... more

2025

This work introduces a modern empirical method for precise radionuclides activity level determination of bulk samples. The unique feature of this method is a practical formula, normalized using far sample-detector geometry at 20 cm, of the free summing coincidence source 137 Cs. The present procedure succeeds in treating the sum peak and the solid angle of the high purity germanium (HPGe) detector efficiency as a nested value included in the macro-correction factor determination. The natural activity of a given any bulk sample can be determined as a test for this method. Standard 137 Cs, 238 U, 232 Th and 152 Eu bulk gamma-ray sources, as well as 70% HPGe gamma-X detector were used to get the empirical treatment for each strongest and recommended gamma rays of any radionuclide. A computer code was designed using the Python language to help analyze, configure, optimize and give rapid calculation analysis.

2025

Surface activity is an estimation of the radioactive surface contamination and, it is calculated using an expression that takes into account the instrument efficiency that is determined by its calibration. Such calibration is performed using sources that barely exhibit similar characteristics to the contaminated surface. Several factors such as humidity, dust, types of surface, source-to-detector distance, source geometry and efficiency affect the surface monitoring. On field conditions there are varieties of materials, equipment and types of contamination, so it is important to consider the effects of these factors on the measurements of surface activity and on the determination of the minimum detectable concentration. MDC is the smallest activity concentration that is practically achievable to be measured by a given instrument under a type of measurement procedure. MDC values must be smaller than the derived limits for surface contamination, so it is an important criterion to sele...

2025, Applied Radiation and Isotopes

Some radon related parameters have been determined through two different techniques (passive and active) in soil and phosphogypsum samples. Emanation factors determined through these techniques show a good agreement for soil samples while for phosphogympsum samples appear large discrepancies. In this paper, these discrepancies are analyzed and explained if non-controlled radon leakages in the passive technique are taken into account.

2025

Measurements of radon concentration were carried out at indoor air of 30 elementary and secondary schools in Kosovo. The aim of this study was to know the level of indoor radon concentration in these locations and to enhance the national radon survey. The main method for indoor radon measurement was direct sampling in alpha scintillation cells and continuous monitoring during some days. However, in cases with an increased instantaneous and continuous radon concentration the additional method of track-etech detectors were applied. The radon concentration was measured to be from 35 Bq m -3 to 814 Bq m -3 and the annual effective doses was calculated to be from 0,28 mSv year -1 to 6,47 mSv year -1 . In most of the schools the concentration and annual effective doses for students and teachers exceeded the limit of ICRP recommendations but in three of them the concentration and annual effective doses are higher.

2025

The purpose of this paper is to increase our understanding of how designers perceive the development in the discipline. It explores the designer's role in working with system transformation and transition and exemplifies how design methods and processes may contribute. The research study builds on interviews and observations in a research project at the transport solution provider Scania. To contribute strategically, designers needed to work in a multidisciplinary manner, involving other disciplines in the client firm. Furthermore, the increased attention in design thinking made the client firms ask designers to facilitate interdisciplinary workshops. Today, the design offering has become more complex, and designers are involved in activities aiming for a change in complex socio-technical systems, which has led to a shift in the designer's role, from working in an intradisciplinary manner to becoming a stakeholder in transdisciplinary work applying methods from the system thinking field.

2025, Radiation Protection Dosimetry

Terrestrial gamma radiation is one of the important radiation exposures on the earth's surface that results from the three primordial radionuclides 226 Ra, 232 Th and 40 K. The elemental concentration of these elements in the earth's crust could result in the anomalous variation of the terrestrial gamma radiation in the environment. The geology of the local area plays an important role in distribution of these radioactive elements. Environmental terrestrial gamma radiation dose rates were measured around the eastern coastal area of Odisha with the objective of establishing baseline data on the background radiation level. The values of the terrestrial gamma radiation dose rate vary significantly at different locations in the study area. The values of the terrestrial gamma dose rate ranged from 77 to 1651 nGy h 21 , with an average of 230 nGy h 21 . During the measurement of the terrestrial gamma dose rate, sand and soil samples were also collected for the assessment of natural radionuclides. The activities of 226 Ra, 232 Th and 40 K from these samples were measured using a gamma-ray spectrometry with a NaI(Tl) detector.

2025, Applied Radiation and Isotopes

Elemental analysis and radioactivity measurement were carried out for nuclear fuel CRUD samples. Ratio of 58 Co radioactivity to Ni content provides a means to enhance the data credibility. Radioactivity ratio of 58 Co to 60 Co was used... more

2025, Applied Radiation and Isotopes

2025

In-depth knowledge regarding the biological effects of the radiation field in space is required for assessing the radiation risks in space. Within the last 50 years, space technology has provided tools for transporting terrestrial life beyond this protective magnetic field in order to study in situ responses to selected conditions of space (reviewed in Horneck et al., 2010). From a biological perspective applicable to simple and complex organisms (ranging from biomolecules and microorganisms to humans) various influential physical modifications such as increased radiation exposure were experienced onboard an orbiting spacecraft in low Earth orbit (LEO), out- and inside the International Space Station (ISS), orbiting Moon or on the way to other astrobiological-interesting targets (Mars or icy moons of Saturn or Jupiter). The majority of experiments on microorganisms in space were performed using Earth-orbiting robotic spacecraft, e.g., the Russian Foton satellites (FOTON) and the Eur...

2025

The aim of this study was to simultaneously measure personal radio frequency-electromagnetic fields (RF-EMFs) exposure using two measurement devices. A body-worn personal exposimeter and a head-worn personal distributed exposimeter were used for measuring body and head exposures, respectively, in 15 microenvironments in Melbourne. The summary statistics obtained for total RF-EMF exposure showed a high representativeness (r² > 0.87 for two paths in the same area). The results obtained during simultaneous measurements using the two devices showed high correlations: r² = 0.94 for the median along the measured paths).

2025, Ambio

The tin mining activities in the suburbs of Jos, Plateau State, Nigeria, have resulted in technical enhancement of the natural background radiation as well as higher activity concentrations of primordial radionuclides in the topsoil of mining sites and their environs. Several studies have considered the radiological human health risks of the mining activity; however, to our knowledge no documented study has investigated the radiological impacts on biota. Hence, an attempt is made to assess potential hazards using published data from the literature and the ERICA Tool. This paper considers the effects of mining and milling on terrestrial organisms like shrubs, large mammals, small burrowing mammals, birds (duck), arthropods (earth worm), grasses, and herbs. The dose rates and risk quotients to these organisms are computed using conservative values for activity concentrations of natural radionuclides reported in Bitsichi and Bukuru mining areas. The results suggest that grasses, herbs, lichens, bryophytes and shrubs receive total dose rates that are of potential concern. The effects of dose rates to specific indicator species of interest are highlighted and discussed. We conclude that further investigation and proper regulations should be set in place in order to reduce the risk posed by the tin mining activity on biota. This paper also presents a brief overview of the impact of mineral mining on biota based on documented literature for other countries.

2025, Medycyna pracy

The current system of dosimetric quantities has been defined by the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU). Complexity of the system implies the physical nature of ionizing radiation, resulting from the presence of different types of radiation of different ionization capabilities, as well as the individual radiation sensitivity of biological material exposed. According to the latest recommendations, there are three types of dosimeter quantities relevant to radiation protection and radiological assessment of occupational exposure. These are the basic quantities, safety quantities and operational quantities. Dose limits for occupational exposure relate directly to the protection quantities, i.e. the equivalent dose and effective dose, while these quantities are practically unmeasurable in real measurement conditions. For this reason, in the system of dosimetric quantities directly measurabl...

2025, Environmental Pollution

EDTA degradation products have significant influence on the mobility of hazardous elements. Sorption behavior was consistent with equilibrium speciation modeling.

2025, Scientific Reports

Radionuclide concentrations in environmental samples such as surface soils, plants and water were evaluated by high purity germanium detector measurements. The contribution rate of short half-life radionuclides such as 132 I to the exposure dose to residents was discussed from the measured values. The highest values of the 131 I/ 137 Cs activity ratio ranged from 49 to 70 in the environmental samples collected at Iwaki City which is located to the south of the F1-NPS. On the other hand, the 132 I/ 131 I activity ratio in the same environmental samples had the lowest values, ranging from 0.01 to 0.02. By assuming that the 132 I/ 131 I activity ratio in the atmosphere was equal to the ratio in the environmental samples, the percent contribution to the thyroid equivalent dose by 132 I was estimated to be less than 2%. Moreover, the contribution to the thyroid exposure by 132 I might be negligible if 132 I contamination was restricted to Iwaki City. n March 11, 2011, the power supplies for the cooling systems in the Fukushima Dai-ichi Nuclear Power Station (F1-NPS) were lost due to tsunami damage following the magnitude 9.0 Great East Japan earthquake 1,2 . Loss of cooling functions led to hydrogen explosions in three reactor units in the F1-NPS and artificial radionuclides such as radioiodine and radiocesium were released from the reactor buildings. These radionuclides have been detected around the world . The most contaminated area in Fukushima Prefecture has been observed to the northwest from the F1-NPS 8 . On March 12, the Japanese Government had ordered the evacuation of residents within a 20-km radius area from the F1-NPS. A screening survey of radionuclide contamination of evacuees was carried out based on the evacuation decision. A first team of radiological professionals from Hirosaki University carried out the screening survey from March 15 to 19, 2011 at evacuation shelters and public facilities in Fukushima Prefecture 9 . The team had two purposes: to carry out the screening survey for evacuees and to evaluate ambient dose rate and activity concentrations. In such a nuclear power station accident with large releases of radioactive contaminates from the reactor containment, special attention must be paid to internal exposure to the thyroid by inhalation of released 131 I and 132 I. 131 I and 132 I have half-lives of 8 days and 2.3 hours, respectively, and therefore it is necessary to make air-borne activity measurements of these radionuclides quickly. Local health authorities measured the dose rate in the thyroid of 1,149 children under the age of 15 by 1-inch 3 1-inch NaI(Tl) scintillation survey meter from March 24 to 30, 2011 10 . Tokonami et al. 11 measured the thyroid doses for 62 evacuees (including infants) using a 3inch 3 3-inch NaI(Tl) scintillation spectrometer and estimated the thyroid equivalent doses of all of them were below 50 mSv. However, contributions to the thyroid equivalent dose of 132 I and 132 Te as short half-life

2025, Health Physics

The RADTRAN and RISKIND transportation risk analysis computer codes are the primary tools used to estimate dose consequences and risks associated with the transport of radioactive material. Over the years, some of the mathematical models used within the two computer codes have been updated and the methodologies to calculate input parameters have been improved. In addition, both codes have been evaluated for ease of use and appropriateness of application and verified against other computer codes that perform similar calculations. However, neither code has been validated against experimental data. This report discusses the results of five sets of experimental measurements used to partially validate the specific mathematical models used to predict the dose to an individual due to a passing shipment of radioactive material within the RADTRAN and RISKIND computer codes. Based on the comparisons it was found that RISKIND most closely predicted the measured dose in the majority of the investigated scenarios and that 12 out of 14 cases demonstrate the expected inverse relationship between the measured dose and the distance of closest approach. Only half of the data demonstrated the expected inverse relationship between dose and speed of travel.

2025, Journal of Radiological Protection

In this paper we present an atmospheric dispersion scenario for a proposed nuclear power plant in Pakistan involving the hypothetical accidental release of radionuclides. For this, a concept involving a Lagrangian stochastic particle model (LSPM) coupled with an Eulerian regional atmospheric modelling system (RAMS) is used. The atmospheric turbulent dispersion of radionuclides (represented by non-buoyant particles/neutral traces) in the LSPM is modelled by applying non-homogeneous turbulence conditions. The mean wind velocities governed by the topography of the region and the surface fluxes of momentum and heat are calculated by the RAMS code. A moving least squares (MLS) technique is introduced to calculate the concentration of radionuclides at ground level. The numerically calculated vertical profiles of wind velocity and temperature are compared with observed data. The results obtained demonstrate that in regions of complex terrain it is not sufficient to model the atmospheric dispersion of particles using a straight-line Gaussian plume model, and that by utilising a Lagrangian stochastic particle model and regional atmospheric modelling system a much more realistic estimation of the dispersion in such a hypothetical scenario was ascertained. The particle dispersion results for a 12 h ground release show that a triangular area of about 400 km 2 situated in the north-west quadrant of release is under radiological threat. The particle distribution shows that the use of a Gaussian plume model (GPM) in such situations will yield quite misleading results.

2025, Japan Geoscience Union

Large amounts of radioactive materials were released into the environment after the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident caused by the Tohoku Earthquake and Tsunami on March 11 2011. As one form of radioactive material emitted into the atmosphere, Cs-bearing radioactive spherical microparticle, known as Cs ball, has gathered attention in recent years. The Cs-ball was first found in aerosols collected at Tsukuba during March 14 and 15 2011 and identified as a water-insoluble glass material containing various heavy metals derived from fission products (FPs) of the nuclear fuel. While recent investigations suggest the widespread distribution of similar particulate radioactive materials in the environment such as soils sampled from the Fukushima prefecture, the distribution of such radioactive particles in the Kanto region including the capital Tokyo just after the accident is still unclear. The present study thus focuses on suspended particulate matter (SPM) filter sa...

2025, Science of the Total Environment

Indoor radon exposure is a significant public health concern, as it is the second leading cause of lung cancer
globally. This systematic review evaluated radon concentrations and associated health risks in Nigerian build-
ings, including homes, schools, and workplaces, through various monitoring techniques such as CR-39 detectors
and RAD7 monitors. A total of 47 eligible studies were included following PRISMA guidelines that covered the spatial variations of radon exposure across Nigeria, revealed a weighted mean indoor radon concentration of 104
Bq/m3, exceeding the WHO reference level of 100 Bq/m3 but below the USEPA action level of 148 Bq/m3.
Certain locations such as Odo-Ona, Ibadan, recorded 531.85 Bq/m3, corresponding to an annual effective dose of
13.42 mSv/yr, an excess lifetime cancer risk of 51.66 × 10 3, and an estimated lung cancer burden of 242 cases/
year per million people. Other regions, including Sokoto Metropolis and Oke-Ogun, also exceeded safety limits,
while coastal areas like Lagos showed the lowest concentrations (7.52 Bq/m3). Geographic disparities were
evident, with southwestern Nigeria showing the highest risk and accounting for 63 % of studies, while northern
and southeastern regions remain underrepresented. Comparative analysis revealed that Nigerian hotspots sur-
pass radon levels reported in several radon-prone countries, including Bulgaria and Northwest Spain, high-
lighting a significant health risk. This review presents Nigeria's first indoor radon exposure map in residential and
occupational settings nationwide that clearly identified critical hotspots and emphasizing the urgent need for
targeted interventions. Awareness of the presence of radon and its potential health effects is very low in Nigeria.
Radon mitigation should integrate geological assessments with radon-resistant construction materials, proper
ventilation, and sealed entry points, especially in uranium-rich and permeable soils. Public awareness, routine
monitoring, and regulatory policies are essential, while future research should focus on underrepresented regions
and uncover long-term exposure patterns.

2025, British Journal of Dermatology

Background In xeroderma pigmentosum (XP), the main means of preventing skin and eye cancers is extreme protection against ultraviolet radiation (UVR). Protection is most important for the face. Objectives We aimed to assess how well patients with XP adhere to medical advice to protect against UVR by objectively estimating the mean daily dose of UVR to the face. Methods We objectively estimated the UVR dose to the face in 36 patients with XP and 25 healthy individuals over 3 weeks in the summer. We used a new methodology which combined UVR dose measurements from a wrist-worn dosimeter with an activity diary record of face photoprotection behaviour for each 15-min period spent outside. A protection factor was associated with each behaviour, and the data were analysed using a negative binomial mixed-effects model. The mean daily UVR dose (weighted for DNA damage capacity) to the face in the patients with XP was 0Á13 standard erythemal doses (SEDs) (mean in healthy individuals = 0Á51 SED). There was wide variation between patients (range < 0Á01-0Á48 SED/day). Self-caring adult patients had a very similar UVR dose to the face as cared-for patients (0Á13 vs. 0Á12 SED/day), despite photoprotecting much more poorly when outside, because the self-caring adults were outside in daylight much less. Conclusions Photoprotection behaviour varies widely within the XP group indicating that nonadherence to photoprotection advice is a significant issue. The timing and duration of going outside are as important as photoprotective measures taken when outside, to determine the UVR exposure to the face. This new methodology will be of value in identifying the sources of UVR exposure in other conditions in which facial UVR exposure is a key outcome, particularly in patients with multiple nonmelanoma skin cancers.

2025, Journal of the Air & Waste Management Association

The city of Aldama, Chihuahua, Mexico is located 30 km NNE of Chihuahua city. Three high-volume collectors with PM 10 heads were placed in specific locations in Aldama during the year 2011 to measure radioisotope concentrations in the air. The city area of 16 km 2 was divided into 64 squares of 500 × 500 m. At the vertices of the grid, silt samples were taken between January and June 2011, before the rains began. The concentrations of natural, cosmogenic, and anthropogenic radioactive isotopes were calculated in both filters and silts samples. The isotopes selected for the measurement were 238 U, 232 Th, 7 Be, 137 Cs, and 40 K. Measurements of PM 10 and silts were performed during 2011, coinciding with the accident at Fukushima, Japan, on March 11. For this reason, we could see the 137 Cs in PM 10 increase between April and July; with the arrival of the rains, the 137 Cs concentration began to decrease in the air. The concentration of PM 10 measured by the equipment located at the Mexican Uranium plant (URAMEX, initials in Spanish) that was processing radioactive ores exceeded the standard values in February and March, when the air velocity increases. At City Hall, the concentration of PM 10 surpassed the value of the standard between May and July. This increased concentration is likely due to increased automobile traffic because City Hall is located in the city center. At a private home, the concentration of PM 10 surpassed the standard on several days during the year because the home is located on the outskirts of the city, where most of the streets are not paved. Due to the high concentrations of PM 10 , especially at the collection point located at the private home, it is necessary to start taking steps to mitigate their spread before they cause health problems in the younger population and in older adults. Implications: The radioisotope content found in the PM 10 confirms that the decision to place the Mexican Uranium plant (URAMEX, initials in Spanish) processing radioactive ores near the town of Aldama was not well thought out. Because the monitoring work was carried out in 2011 and coincided with the Fukushima accident, an increased concentration of 137 Cs could be detected in the PM 10 . We made recommendations to the municipal authorities of the city to mitigate the concentration of particles in the air.

2025, Marine Pollution Bulletin

The natural radioactivity levels in sediment samples of the northern coast of Oman Sea, covering the coastal strip from Hormoz canyon to Goatr seaport, as the first time has been determined. The results of measurements will serve as background reference level for Oman Sea coastlines. Sediments from 36 coastal and near shore locations were collected for analysis. Analysis on the collected samples were carried out to determine 235 U, 238 U, 232 Th, 40 K and 137 Cs using two high purity germanium detectors with 38.5% and 55% relative efficiencies. The concentration of 235 U, 238 U, 232 Th, 40 K and 137 Cs in sediment samples ranged between 1.01 and 2.87 Bq/kg, 11.83 and 22.68 Bq/kg, 10.7 and 25.02 Bq/kg, 222.89 and 535.07 Bq/kg and 0.14 and 2.8 Bq/kg, respectively. The radium equivalent activity was well below the defined limit of 370 Bq/kg. The external hazard indices were found to be less than 1, indicating a low dose.

2025, Journal of Environmental Radioactivity

Erosion is a natural process, but it has been dramatically increased by human activities; and this adversely influences soil productivity and environmental quality. For quantification of soil erosion, several techniques including the use of Cs-137 have been employed. This study was conducted to explore the relationships of Cs-137 inventory with magnetic properties in calcareous soils in western Iran. Ten transects were selected in the hilly region in Chelgerd district of Iran. Soil samples from 0 to 30 and 30 e50 cm depths were collected from fifty points to determine Cs-137 inventory, magnetic measures and selected physico-chemical properties (in total there were 100 soil samples). The results showed that simple mass balance model (SMBM) estimated a gross erosion rate of 29.6 t ha À1 yr À1 and a net soil deposition of 21.8 t ha À1 yr À1 ; hence, a net soil loss of 9.6 t ha À1 yr À1 and a sediment delivery ratio of 31.4%. Simple linear regression and non-linear regression analysis showed that mass magnetic susceptibility (c lf ) explained only 33.64% and 45% of variability in Cs-137 in the transects studied. The results of multiple linear regression analysis of 137 Cs with magnetic parameters and physico-chemical properties indicated that extractable potassium and c lf explained approximately 61% of the total variability in 137 Cs in the area studied. Overall, the results suggest that further research is needed for the use of magnetic characteristics as an alternative technique in place Cs-137 methodology for calcareous soils.

2025, Journal of International Environmental Application and Science

Natural radionuclides generally represent the main source of radiation exposure to the public. In the environment, they either arise from the direct release of Radon from ground into ambient air or through dissolution of U-and Th-series members into water. As a consequence the control of natural radionuclides in water for human consumption has become a major goal worldwide during the recent decade. Limitations were set and the need for simple and rapid procedures for their implementation becomes necessary. Liquid scintillation techniques provide the detection and quantification of alpha and beta emitters in aqueous sample. Liquid Scintillation Counter (LSC) techniques using Pulse Shape Discrimination (PSD) allow counting of alpha and beta radiation in the same sample simultaneously. In this study, Packard Tricarb 3170 TR-SL LSC has been used. Ultima Gold LLT produced by Packard Instrument Company was used as the liquid scintillator. The optimum counting parameters and Pulse Shape Di...

2025, Radiation Protection Dosimetry

The realisation of the geographical distribution of the indoor radon concentrations in dwellings represents a valuable tool necessary for assessing the public exposure. In this work are reported the results of the indoor radon obtained in the first stage of the survey involving 247 measurements. From the preliminary information on ∼10 % of the territory, covering the biggest cities in Albania results on indoor radon concentrations ranging from 14 to 1238 Bq m 23 with an arithmetic mean of 120+ + + + +67 Bq m 23 . The population-weighted average indoor radon concentration was calculated to be 101 Bq m 23 . The adopted survey strategy highlighted the necessity for the future stages to spread the measurements in order to cover the entire territory of Albania, instead of remaining focused only on the demographic criteria.

2025, Radiation Protection Dosimetry

This study focuses on the radiological characterisation of building materials manufactured in Albania by using a highresolution gamma-ray spectrometer. The average activity concentrations of 40 K, 226 Ra and 232 Th were, respectively, 644.1+ + + + +64.2, 33.4 + + + + + 6.4 and 42.2 + + + + + 7.6 Bq kg 21 in the clay brick samples and 179.7 + + + + + 48.9, 55.0 + + + + + 5.8 and 17.0 + + + + + 3.3 Bq kg 21 in the cement samples. The calculated activity concentration index (ACI), varied from 0.48+ + + + +0.02 to 0.63+ + + + +0.04 in the clay brick samples and from 0.29+ + + + +0.03 to 0.37+ + + + +0.02 in the cement samples. Based on the ACI, all of the clay brick and cement samples were categorised as A1 materials. The authors can exclude (at 3s level) any restriction of their use as bulk materials.

2025, Applied Radiation and Isotopes

of the transfer of 234 U and 238 U during water-rock interactions in the Cammenellis granite (Cornwall, England) and implications for the interpretation of field data. Applied Radiation and Isotopes. V. 54 pp. 977-994. CETESB. Guia de... more

2025, ArXiv

The concern on human health is often overseen while wearable technologies attract exploding interests. Mainly due to the extreme proximity or a direct physical contact to the human skin, wearable communications devices are acknowledged to cause higher levels of specific absorption rate (SAR) at the skin surface. Unfortunately, so far, we have found no study encompassing all the aspects that the general public needs to understand about wearable technologies--i.e., the analytical and experimental backgrounds, and report of SAR levels generated from commercial wearable devices. In this context, this paper provides an extensive review on SAR from various commercial wearable devices that are currently sold in the market, as well as the analytical framework and the current measurement methodologies for standard compliance tests. Moreover, considering the present interest in millimeter wave (mmW), this paper sheds light on the SAR evaluated at 60 GHz and also compares the SAR to that measu...

2025, Journal of Radiation Research

2025, Radiation and Environmental Biophysics

In this study, which is the first of its kind in the gulf region, eye doses of interventional cardiologists and nurses were measured using active dosimeters for left and right eyes, in 60 percutaneous coronary interventions in three main hospitals in Kuwait. The dose given in terms of H p (0.07) per procedure when ceiling suspended screens were used by main operators ranged from 18.5 to 30.3 µSv for the left eye and from 12.6 to 23.6 µSv for the right eye. Taking into account typical staff workload, the results show that the dose limit of 20 mSv/year to the eyes can be exceeded for interventional cardiologists in some situations, which demonstrates the need of using additional effective radiation protection tools, e.g. protective eye spectacles, in addition to the regular and proper use of ceiling suspended screens. With indications of increase in workload, the need for availability of a dedicated active dosimeter for the regular monitoring of eye doses is emphasized.

2025, Elsevier

Indoor radon exposure is a significant public health concern, as it is the second leading cause of lung cancer
globally. This systematic review evaluated radon concentrations and associated health risks in Nigerian buildings, including homes, schools, and workplaces, through various monitoring techniques such as CR-39 detectors
and RAD7 monitors. A total of 47 eligible studies were included following PRISMA guidelines that covered the spatial variations of radon exposure across Nigeria, revealed a weighted mean indoor radon concentration of 104
Bq/m3
, exceeding the WHO reference level of 100 Bq/m3 but below the USEPA action level of 148 Bq/m3
.
Certain locations such as Odo-Ona, Ibadan, recorded 531.85 Bq/m3
, corresponding to an annual effective dose of
13.42 mSv/yr, an excess lifetime cancer risk of 51.66 × 10− 3
, and an estimated lung cancer burden of 242 cases/
year per million people. Other regions, including Sokoto Metropolis and Oke-Ogun, also exceeded safety limits,
while coastal areas like Lagos showed the lowest concentrations (7.52 Bq/m3
). Geographic disparities were
evident, with southwestern Nigeria showing the highest risk and accounting for 63 % of studies, while northern
and southeastern regions remain underrepresented. Comparative analysis revealed that Nigerian hotspots surpass radon levels reported in several radon-prone countries, including Bulgaria and Northwest Spain, highlighting a significant health risk. This review presents Nigeria's first indoor radon exposure map in residential and
occupational settings nationwide that clearly identified critical hotspots and emphasizing the urgent need for
targeted interventions. Awareness of the presence of radon and its potential health effects is very low in Nigeria.
Radon mitigation should integrate geological assessments with radon-resistant construction materials, proper
ventilation, and sealed entry points, especially in uranium-rich and permeable soils. Public awareness, routine
monitoring, and regulatory policies are essential, while future research should focus on underrepresented regions
and uncover long-term exposure patterns

2025, Health Physics

The counting efficiencies of the phantoms for lZ5I were measured at different phantom-todetector distances. The anthropomorphic characteristics of the phantoms have been compared with the average man parameters. It was concluded that the BRMD, American National Standards Institute, and Radiology Support Devices phantoms have the same performance characteristics when the neck-todetector distances are greater than 12 cm and all phantoms are essentially equivalent at 30 cm or more. The Kyoto Kagaku Hyohon phantom showed lower counting efficiencies at phantom-to-detector distances less than 30 cm. This was attributed to the design of the phantom. This study has also shown that the phantom need not be highly anthropomorphic provided the calibration is not performed at short neckdetector distances. Indeed, it might be possible to use a simple point source of '''1 placed behind a 1.5 cm block of lucite at neck detector distances of 12 cm or more.

2025, Radiation Protection Dosimetry

The detonation of a radiological dispersion device may result in a situation where individuals inhale radioactive materials and require rapid assessment of internal contamination. The feasibility of using a 2×2-inch sodium-iodide detector to determine the committed effective dose to an individual following acute inhalation of gamma-emitting radionuclides was investigated. Experimental configurations of point sources with a polymethyl methacrylate slab phantom were used to validate Monte Carlo simulations. The validated detector model was used to simulate the responses for four detector positions on six different anthropomorphic phantoms. The nuclides examined included 241 Am, 60 Co, 137 Cs, 131 I and 192 Ir. Biokinetic modelling was employed to determine the distributed activity in the body as a function of post-inhalation time. The simulation and biokinetic data were used to determine time-dependent count-rate values at optimal detector locations on the body for each radionuclide corresponding to a target committed effective dose (E50) value of 250 mSv.

2025, Health Physics

Following a radiation emergency, evacuated, sheltered or other members of the public would require monitoring for external and/or internal contamination and, if indicated, decontamination. In addition, the potentially-impacted population would be identified for biodosimetry/bioassay or needed medical treatment (chelation therapy, cytokine treatment, etc.) and prioritized for follow-up. Expeditious implementation of these activities presents many challenges, especially when a large population is affected. Furthermore, experience from previous radiation incidents has demonstrated that the number of people seeking monitoring for radioactive contamination (both external and internal) could be much higher than the actual number of contaminated individuals. In the United States, the Department of Health and Human Services is the lead agency to coordinate federal support for population monitoring activities. Population monitoring includes (1) monitoring people for external contamination; (2) monitoring people for internal contamination; (3) population decontamination; (4) collecting epidemiologic data regarding potentially exposed and/or contaminated individuals to prioritize the affected population for limited medical resources; (5) administering available pharmaceuticals for internal decontamination as deemed necessary by appropriate health officials; (6) performing dose reconstruction; and (7) establishing a registry to conduct long-term monitoring of this population for potential long-term health effects. This paper will focus on screening for internal contamination and will describe the use of early epidemiologic data as well as direct bioassay techniques to rapidly identify and prioritize the affected population for further analysis and medical attention.

2025

Preface The first edition of Population Monitoring in Radiation Emergencies was published in 2007 after extensive collaboration with representatives from many local, state, and federal agencies and nongovernmental organizations who provided expert input. Since the publication of the 2007 edition, the Centers for Disease Control and Prevention (CDC) staff and its partners have presented the content of this guide at national and regional technical meetings and training sessions throughout the country to a variety of public health audiences. The content of the guide has been used in the design and conduct of drills and exercises at local, state, and federal levels. States are beginning to incorporate population monitoring into their radiation emergency response plans as awareness of this important preparedness element continues to increase. The operational concept of the community reception center (CRC)—first described in the 2007 edition—is also being incorporated in radiation emergen...

2025, NKS Secretariat

In a previous NKS project " OPTIMETHOD" (2018OPTIMETHOD" ( -2019)), an optimised method was presented for separation of Pu, Am and Cm isotopes from NPP reactor water samples. This separation method was tested in an intercomparison organised in 2020 with two solid sample matrices, lichen sample and IAEA-384 reference material, for expanding its usability. The goal of the RAD-MERDE project was to provide an alternative, novel method to previously used fairly established methods for separating actinide isotopes from e.g. environmental and nuclear decommissioning samples. The tested separation method includes iron hydroxide coprecipitation of actinide isotopes and radiochemical separation of Pu and Am with extraction chromatography resins TEVA and DGA. The obtained practical experiences and analytical performance for Pu and Am are discussed in this report and the findings suggest that the development and testing of the separation method should be continued with more solid sample materials.

2025, Journal of Environmental Chemical Engineering

Decontamination after a nuclear or radiological release requires a detailed understanding of the materials hosting the contamination, the chemistry of the radionuclide, and the chemical properties of the decontamination agent. Urban contamination via a number of radiological release scenarios may require simple decontamination methods that can be deployed for wide-area decontamination. This paper investigates a number of factors of importance for developing such decontamination methods, focusing on cesium. These factors include the influence on decontamination approaches from the cesium deposition conditions, the urban building material composition and, when washing with an ionic solution that is utilized for decontamination, the composition of the wash solutions. In summary, the sorption chemistry of cesium onto urban building materials and roadways has been studied to develop simple decontamination methods that can be deployed for wide-area decontamination efforts. To improve the understanding of the sorption of cesium onto common urban building materials and roadways the desorption of cesium deposited from solution and as a dry powder was tested. Using ammonium (NH 4 + )salt solutions, we tested the desorption of ionic cesium bound to individual components of concrete and coupons of several common building materials. While the tests on concrete aggregate suggest that a concentration >10 mM NH 4 + does not improve the desorption of cesium, tests on concrete, asphalt, marble, limestone and granite monoliths showed improved decontamination factors when the NH 4 + concentration increased from 0.1 to 0.5 M. We also found that cesium as dry particulate material could be removed quite effectively although the contamination became tenacious upon wetting the surface.

2025, Anadolu kardiyoloji dergisi : AKD = the Anatolian journal of cardiology

The radial approach has been increasingly used as an alternative to femoral access. The purpose of the present study was to assess the feasibility, success, and safety of the transradial approach (TRA) for diagnostic coronary angiography, and to describe the difficulties associated with the technique as compared with transfemoral approach (TRF). A series of 180 consecutive patients were divided to TRA or TFA groups by two operators. We compared the groups regarding procedural time, access time, fluoroscopy time, procedural failure, complications, contrast volume, length of hospital stay, and number of used coronary catheters. The number of used coronary catheters was not different between the two groups (p = 0.6). Total hospital length of stay was significantly shorter in the radial group (p <0.0001) than in femoral one. We found differences between the radial and femoral groups in the success rate (p<0.0001), contrast volume (p = 0.012), procedural time (p<0.0001), access ...

2025

Samples of Trinitite and soil from Trinity site were studied in the radioactivity measurements laboratory at the University of Bremen and at the authors’ facilities in Anaheim (JCR) and Edgewater (WMK). Gamma spectroscopy was used to identify and quantify radionuclides in Trinitite and to perform a radiometric characterization of soil at the Trinity site. Additionally, a similar material (“atomsite“) formed during a soviet test at the Semipalatinsk nuclear test site was investigated. Fission products (137Cs, 155Eu) together with activation products (60Co, 133Ba, 152Eu, 154Eu, 241Am) and 239Pu were identified. A literature search including some publicly available archive sources was conducted and our data compared to previously published results. Obtained data on Trinitite were also compared to literature data on atomsite formed during atmospheric nuclear tests in Algeria. Variability of radioactivity in Trinitite and relationship of distance from the ground zero and activation were ...

2025, Radiation Protection Dosimetry

On the occasion of the 20th anniversary of the Chernobyl accident an attempt has been made to evaluate the impact of the Chernobyl accident on the global burden of human cancer in Europe. This required the estimation of radiation doses in each of the 40 European countries. Dose estimation was based on the analysis and compilation of data either published in the scientific literature or provided by local experts. Considerable variability has been observed in exposure levels among the European populations. The average individual doses to the thyroid from the intake of 131 I for children aged 1 y were found to vary from 0.01mGyinPortugalupto750mGyinGomelOblast(Belarus).Thyroiddosestoadultswereconsistentlylowerthanthedosesreceivedbyyoungchildren.Theaverageindividualeffectivedosesfromexternalexposureandingestionoflong−livedradiocaesiumaccruedintheperiod1986−2005variedfrom0.01 mGy in Portugal up to 750 mGy in Gomel Oblast (Belarus). Thyroid doses to adults were consistently lower than the doses received by young children. The average individual effective doses from external exposure and ingestion of long-lived radiocaesium accrued in the period 1986-2005 varied from 0.01mGyinPortugalupto750mGyinGomelOblast(Belarus).Thyroiddosestoadultswereconsistentlylowerthanthedosesreceivedbyyoungchildren.Theaverageindividualeffectivedosesfromexternalexposureandingestionoflong−livedradiocaesiumaccruedintheperiod1986−2005variedfrom0 in Portugal to $10 mSv in Gomel Oblast (Belarus) and Bryansk Oblast (Russia). The uncertainties in the dose estimates were subjectively estimated on the basis of the availability and reliability of the radiation data that were used for dose reconstruction in each country.

2025, Journal of Environmental Radioactivity

The Euratom BSS requires that in the near future (2015) the building materials for application in dwellings or buildings such as offices or workshops are screened for NORM nuclides. The screening tool is the activity concentration index (ACI). Therefore it is expected that a large number of building materials will be screened for NORM and thus require ACI determination. Nowadays, the proposed standard for determination of building material ACI is a laboratory analyses technique with high purity germanium spectrometry and 21 days equilibrium delay. In this paper, the B-NORM method for determination of building material ACI is assessed as a faster method that can be performed on-site, alternative to the aforementioned standard method. The B-NORM method utilizes a LaBr 3 (Ce) scintillation probe to obtain the spectral data. Commercially available software was applied to comprehensively take into account the factors determining the counting efficiency. The ACI was determined by interpreting the gamma spectrum from 226 Ra and its progeny; 232 Th progeny and 40 K. In order to assess the accuracy of the B-NORM method, a large selection of samples was analyzed by a certified laboratory and the results were compared with the B-NORM results. The results obtained with the B-NORM method were in good correlation with the results obtained by the certified laboratory, indicating that the B-NORM method is an appropriate screening method to assess building material ACI. The B-NORM method was applied to analyze more than 120 building materials on the Belgian market. No building materials that exceed the proposed reference level of 1 mSv/year were encountered.

2025

Uranium-series data for groundwater samples from the vicinity of the Nopal I uranium ore deposit are used to place constraints on radionuclide transport and hydrologic processes at this site, and also, by analogy, at Yucca Mountain. Decreasing uranium concentrations for wells drilled in 2003 suggest that groundwater flow rates are low (< I O m/yr). Field tests, well productivity, and uranium isotopic constraints also suggest that groundwater flow and mixing is limited at this site. The uranium isotopic systematics for water collected in the mine adit are consistent with longer rockwater interaction times and higher uranium dissolution rates at the front of the adit where the deposit i s located. Short-lived nuclide data for groundwater wells are used to calculate retardation factors that are on the order of 1,000 for radium and 10,000 to 10,000,000 for lead andpolonium. Radium has enhanced mobility in adit water andfractures near the deposit. ' mass spectrometry.

2025, Health Physics

This paper presents a fundamental investigation of the screening of intakes and the estimation of internal doses for workers at a biomedical research facility from their urinary excretion data. Urine samples from the workers were collected immediately before and several days after handling radioactive materials, and 5-mL portions were measured directly with a sodium iodide scintillation detector or a liquid scintillation detector. Intakes of radionuclides and effective doses were estimated from the data using the Internal Dose Easy Calculation code. Blank levels of radioactivity and detection limits for this method were determined from the radioactivity contained in urine samples collected from volunteers working outside the controlled area (control samples). Most of the radioactivity in the control samples was attributed to 40 K. Under the present experimental conditions, the detection limits for the committed effective doses were 7.5 ؋ 10 ؊4 mSv for 125 I and 6.9 ؋ 10 ؊2 mSv for 35 S in the case of samples collected 1 d after handling. Accordingly, it can be determined whether workers were exposed more than the recording level (1 mSv of committed effective dose) or not. No workers in the surveyed facility were found to suffer internal exposure beyond the recording levels, and their intakes were estimated to be below the detection limits in the 2-y investigation period. In an ordinary facility of biomedical research, the amount of unsealed radioactivity handled at one time is within 10 MBq in many cases, and the air ventilation and filtering systems work adequately. Under such circumstances, the present results suggest that individual monitoring, such as urine analysis, is omissible in many cases as a routine monitoring of internal exposure for workers.

2025, Journal of Applied Clinical Medical Physics

The use of a radioactive check device containing Strontium 90 was investigated to carry out the redundancy checks of Farmer-type ionization chambers. It was not possible to meet the recommended tolerance limits of the redundancy checks without taking into account the angular response of the ionization chambers. The ionization chambers exhibited a maximum variation of 1% in the angular response in this check device. After accounting for the angular response the maximum variation of the short-term repeatability was 0.14% with a standard deviation of Ϯ0.05%. The long-term constancy checked over a period of nine months was less than Ϯ0.6% for measurements, taking into account the angular response of the ionization chambers. No significant effect of the background radiation levels was observed on the measurements.

2025, Journal of radiological protection : official journal of the Society for Radiological Protection

2025

During the operations of nuclear facilities and during the environmental remediation and decommissioning of nuclear facilities, radioactive waste is generated which must be assayed. To save on labor and transportation costs, this material is commonly placed in large containers of typically several cubic meters in size [e.g. B-25]. The most common choices of assay are to either extract a representative sample of the contents for laboratory assay, or to use in-situ gamma spectroscopy of the total container. Both of these methods have strengths and weaknesses. InSitu methods determine container activity directly and typically quantify gamma emitters which are then correlated to total activity. Gamma measurement accuracy can suffer from an inadequate efficiency calibration, which can be caused by variations in container size, shape, matrix fill height, or matrix density, but primarily by non-homogeneous distribution of the radioactivity. Laboratory assay methods using a small sample extracted from the container are generally quite accurate for the sample analyzed; but the determination of total container activity requires the assumption that the sample analyzed in the laboratory is truly representative of the total container, which is also heavily influenced by the non-homogeneous distribution of the radioactivity. This evaluation attempts to determine the best way to estimate the activity within the container and gives quantitative estimates of measurement uncertainty for various conditions of radioactivity contained within the container and for various in-toto and sampling strategies. A new feature of the ISOCS [In-Situ Object Counting System] software called IUE [ISOCS Uncertainty Estimator] was used. First, the various parameters were examined which cause uncertainty in the in-toto measurement to evaluate those which are the major contributors and to asses the measurement uncertainty for a uniformly distributed sample. Next, a series of levels of non-homogeneous distributions were analyzed with a variety of potential detector placement strategies. These variables included number of detectors, placement of the detectors, and movement of the detectors. The uncertainty due to non-homogeneity is reduced when the detectors are moved away from the container, when more detector positions are used, and when the detectors are scanned. When the contents of the container are not homogeneous, the sampling uncertainty is likely to be larger than the in-toto measurement uncertainty. For those same non-homogeneous sample situations, various sampling strategies were tried, including type of sample extraction method, size of sample extracted, and number of samples extracted. The conclusion is that if the contents of the container are not homogeneous, the uncertainty due to the sampling process is likely to be larger than the in-toto measurement uncertainty.

2025, Health Physics

The measurement of exposure rates is fundamentally important in the release of patients given radioactive materials and for keeping the exposures of others as low as reasonable achievable. Similar measurement methodologies have generally been used for point and extended sources, but this approach may lead to methodological errors in calculating radiation dose estimates. In this study, nuclear medicine patients who received high activities of Na 131 I for therapy were monitored using different measurement methodologies, and the results showed that the usual measurement performed at 1.0 m in front of the body resulted in a mean error of 40% between experimental and theoretical exposure rates. The best measurements were obtained when performed at 2.0 m in front of the patients. With this approach, the error was about 2% between experimental and theoretical values. These findings suggest a new methodology for patients' measurement in nuclear medicine and could be useful for personal monitoring in cases of radiological emergencies involving 131 I ingestion.