Radioactive Materials Research Articles

Regulatory requirements to support a specific regulation of oil norm waste in Brazil.

The oil and natural gas industry is one of the largest producers of Naturally Occurring Radioactive Material (NORM) worldwide. The scale and sludge are NORM wastes with the highest activity concentration levels, reaching 3500Bq per g of 226Ra (scale). As wastes (sludge, scale, and produced water) are constantly produced in routine activities, a specific regulation for these wastes is necessary. Therefore, this study presents the regulatory requirements that may serve as a basis for the responsible regulatory body to prepare a specific regulation for the NORM waste generated by the oil industry. As a study published showing that the disposal of bulk NORM waste (not packaged wastes) is viable in Brazil, requirements for the management of these wastes and the characteristics of the landfill for disposal were included.

Safety analysis of wind-induced resuspension of radioactive materials from the Techensky reservoir cascade coastline

The paper provides an assessment of the probability and consequences of external events capable of leading to an incident with a breach of established safety barriers restricting the spread of radioactive substances along the coastline of the Techensky reservoir cascade. The initiating events for such an incident could be adverse meteorological conditions resulting in a decrease in the water level in the cascade water bodies below the specified design levels. Drying out the surface of previously inundated sections of the coastline will create an extensive source of atmospheric contamination by technogenic radionuclides during wind-induced resuspension. The probable area of the dried-out sections will be 0.02 — 0.08 kml for reservoir V-3, 0.06 — 0.28 kml for reservoir V-4, 0.19 — 0.90 kml for reservoir V-10, and 0.47 — 2.19 kml for reservoir V-11. The cumulative inventory of 137Cs and 90Sr in the specified area exceeds 105 Bq/ml. The activity released into the atmosphere within an hour will range from 3.69∙108 to 8.48∙1011 Bq for the wind speeds of 5 m/s and 20 m/s, respectively. The probabilities of joint occurrence of strong winds and drought conditions are 6.8∙10-7 per year for a wind speed of 20 m/s and 2.1∙10-3 per year for a wind speed of 5 m/s. The highest values of effective dose for the population of the nearest settlements, reaching 1-3 μSv in the first 10 days and over 200 μSv in the first year, are achieved under extreme wind loads with wind speeds of 20 m/s or more.

Study of Resistance of [Cu3(C6H3(COO)3)2(H2O)3]n (HKUST-1) To Electron Beam at Dosages of 0 to 150 kGy

Abstract Processing radioactive waste remains a formidable task in utilizing radioactive materials due to their inherent toxicity and carcinogenic nature, necessitating treatment before safe release into the environment. Among the methods employed for radioactive waste treatment, adsorption stands out, with considerable attention focused on an emerging adsorbent named [Cu3(C6H3(COO)3)2(H2O)3]n or Hong Kong University of Science and Technology-1 (HKUST-1), renowned for its distinctive properties. HKUST-1, being a porous material, holds promise as an effective agent for radioactive waste adsorption. In this investigation, HKUST-1 was synthesized via the solvothermal technique at 100°C, and its resilience was evaluated under electron beam irradiation at doses ranging from 50 to 150 kGy. Characterization techniques involving SEM, XRD, and adsorption tests were conducted to assess any alterations in HKUST-1’s attributes pre- and post-irradiation. Results revealed modifications in HKUST- 1’s characteristics following electron beam exposure, notably a decline in crystal adsorption quality within the 50 to 125 kGy dose range, indicating amorphization. Additionally, irradiation at 50 and 150 kGy demonstrated a potential for crystallization, thereby augmenting adsorption quality. Remarkably, the most favorable adsorption performance was observed at a 150 kGy irradiation dose, showcasing an average adsorbed gas volume of 332.05 cm3/g, a surface area of 947.747 m2/g, and a pore volume of 0.5586 cm3/g.

Study on Characteristics of Epoxy Resin-Based Plastic Scintillators for Detectors with Simulation Using Monte Carlo Code

Abstract To determine the presence of radioactive materials emitting gamma rays entering or exiting nuclear facilities, ports, airports, international borders, or other strategic locations, radiation portal monitors (RPMs) capable of detecting such gamma radiation need to be installed in these places. National Research and Innovation Agency of Indonesia (BRIN) is currently developing RPMs with detector components made of plastic scintillator based on epoxy resin and augmented with aromatic fluorescent materials to produce visible light, which is the working range of the photomultiplier tube (PMT) or silicon photomultiplier (SiPM). This research aims to study the characteristics of the gamma photon radiation energy spectrum from Co-60, Cs-137, and Ir-192 sources in an epoxy resin plastic scintillator and study the absorbed dose of the scintillator to gamma photon radiation energy from Co-60, Cs-137, and Ir-192 sources as a function of source distance and incidence angle of gamma rays with simulations using the MCNPX code. The scintillator is modeled in the form of a cylinder with a diameter of 5 cm and a height of 5 cm. To simulate the gamma photon radiation energy spectrum in the scintillator, the F4 tally was used and to simulate the scintillator absorbed dose, the F6 tally was used. This simulation used gamma sources of Co-60, Cs-137, and Ir-192 of 1 mCi each. These characteristics of the epoxy resin plastic scintillator have been successfully simulated. Data on the characteristics of epoxy resin plastic scintillators is important to know and study as supporting data in making plastic detectors as part of the manufacture and development of RPM.

Health risk assessment of radiation dose level in oranges and mangoes fruits from farms in Benue State, Nigeria

The health risk and radiation dose level in Oranges and Mangoes due to ingestion from farm locations in Benue State was assessed. A total of fifty (50) samples were collected in five different farm locations in Benue State, the samples were washed with distilled water to remove dirt, a radiation meter was placed 10cm from the fruits and measurements were taken for 30 seconds, background radiation levels and radiation dose level from the fruits were measured and calculated. The results showed that the radiation dose level for Oranges ranged from 1.489 to 2.365 mSv/hr and 1.122 to 1.899 mSv/hr for mangoes and the Annual Equivalent Doses (AED) for Oranges and Mangoes consumption was estimated to be 0.107 and 0.027 mSv/yr, respectively. Both values exceeded the World Health Organization (WHO) and the United States Environmental Protection Agency (USEPA) recommended limit of 1.0 mSv/yr. The high radiation levels could be attributed to naturally occurring radioactive materials in the soil or water, contamination from nearby sources. The Excess Lifetime Cancer Risk (ELCR) was calculated, with values of 0.2677 for Oranges and 0.683 for Mangoes, which are lower than the safe limit specified by WHO. While there is minimal risk associated with radiation exposure from consuming these fruits, further monitoring and investigation are necessary to ensure food safety and security in the study area.

Comparison of Specific Exemption Regulations for Consumer Products Containing Radioactive Isotopes

Background: Practices involving radionuclides at levels below the International Atomic Energy Agency (IAEA) generic exemptions are exempt from regulation without further consideration. Practices involving radionuclides at levels above those generic exemptions may also be exempt from regulation if they meet certain conditions. These are known as specific exemptions, and each country has established its own specific exemption criteria based on the conditions set out in the IAEA General Safety Requirements (GSR) Part 3. Those conditions relate to the physical or chemical form of the radioactive material as well as to its use or the means of its disposal.Materials and Methods: The specific exemption criteria of eight countries (i.e., the United States of America [US], Japan, France, China, Australia, Canada, the United Kingdom of Great Britain and Northern Ireland [UK], and Germany) were analyzed. Their similarities and differences as compared with the specific exemption criteria of the Republic of Korea (ROK) were analyzed, and suggestions for revision of the Korean regulations were formulated.Results and Discussion: Each country’s specific exemption criteria are defined based mostly on the IAEA criteria but tailored to its domestic circumstances. The nine countries with their specific exemption criteria can be broadly categorized into three groups: nuclide-specific exemptions for specific products (the ROK and the US), common criteria for all nuclides without specification of particular products (Japan, France, and China), and both specific and common criteria (Australia, Canada, the UK, and Germany).Conclusion: The specific exemption criteria of the different countries examined in this study could be helpful in reviewing the ROK’s specific exemption criteria. Development of common criteria alongside specific criteria for products requiring special attention may be a good way to determine whether new consumer products containing radioisotopes should be regulated.

Environmental and patient safety: Advances in radiological techniques to reduce radiation exposure

The growing concern for environmental and patient safety in medical imaging has driven significant advancements in radiological techniques aimed at reducing radiation exposure. This review explores these developments, emphasizing the dual focus on minimizing harm to patients and addressing the broader environmental impact of radiological practices. Recent innovations include the optimization of imaging protocols, the introduction of low-dose imaging technologies, and the integration of advanced software algorithms that enhance image quality while reducing the need for higher radiation doses. The implementation of iterative reconstruction techniques, for instance, has allowed for significant dose reductions in computed tomography (CT) scans without compromising diagnostic accuracy. Additionally, the use of alternative imaging modalities such as magnetic resonance imaging (MRI) and ultrasound, which do not involve ionizing radiation, is increasingly recommended where clinically appropriate, further mitigating radiation risks. Furthermore, the shift towards personalized imaging protocols, where radiation doses are adjusted based on individual patient characteristics, marks a critical advance in patient safety. This approach not only reduces unnecessary exposure but also enhances the overall effectiveness of diagnostic procedures. Environmental safety considerations have also led to the development of more sustainable radiological practices, including the safe disposal of radioactive materials and the reduction of energy consumption in imaging facilities. These efforts are aligned with broader healthcare initiatives to lower the carbon footprint of medical practices. The advancements in radiological techniques to reduce radiation exposure reflect a growing commitment to patient-centered care and environmental stewardship in healthcare. As technology continues to evolve, ongoing research and collaboration between medical professionals, physicists, and environmental scientists will be crucial in furthering these goals. By continuing to innovate and implement safer radiological practices, the medical community can significantly mitigate the risks associated with radiation exposure, ensuring better health outcomes for patients and reducing the environmental impact of radiological services.

방사성 물질 흡착용 활성탄소섬유 시험방법 연구

The global demand for energy is escalating due to the increased power consumption for AI data centers, leading to the expansion of nuclear power facilities and a subsequent rise in radioactive waste generation. To address this, activated carbon filter systems have been employed in nuclear power plants to adsorb and prevent the atmospheric release of radioactive iodine, a byproduct of these facilities. However, the substantial annual discharge of activated carbon is causing challenges such as a shortage of waste storage facilities. To mitigate this issue, this study investigated the application of activated carbon fiber (ACF) in nuclear power plant filter systems. Adhering to existing standards for radioactive material adsorption, we established a suitable testing environment for ACF and conducted adsorption and removal tests. The results demonstrated a maximum removal efficiency of over 99.918% for radioactive iodine, indicating a performance comparable or superior to that of conventional activated carbon used in current processes. This research is expected to contribute positively to the diversification of materials used for radioactive material adsorption and removal in nuclear power plants, as well as the establishment of relevant standards.

Comprehensive risk management and safety strategies in radiation use in medical imaging

Radiation use in medical imaging, while essential for accurate diagnosis and treatment planning, poses inherent risks that require comprehensive risk management and safety strategies. This review discusses the critical aspects of managing these risks in clinical settings, focusing on patient safety, staff protection, and environmental considerations. A major challenge in medical imaging is balancing the diagnostic benefits of radiation against potential harms, particularly in sensitive populations such as children and pregnant women. Comprehensive risk management involves implementing dose optimization techniques, such as using low-dose imaging protocols and advanced technologies like iterative reconstruction and artificial intelligence (AI) algorithms, which enhance image quality while minimizing exposure. Additionally, ensuring the safety of healthcare staff is paramount. This requires adherence to strict safety protocols, including the use of personal protective equipment (PPE), regular monitoring of radiation levels, and continuous education on safe radiation practices. Institutional policies must also address the proper maintenance and calibration of imaging equipment to prevent unnecessary exposure due to equipment malfunction or improper use. Environmental safety is another critical component, necessitating the safe disposal of radioactive materials and the adoption of energy-efficient technologies to reduce the environmental footprint of medical imaging. Regulatory compliance with international safety standards, such as those set by the International Commission on Radiological Protection (ICRP) and national bodies, is essential for ensuring consistent safety practices across healthcare institutions. Future directions in radiation safety include the integration of digital health technologies to monitor and manage radiation exposure more effectively, and ongoing research into novel imaging techniques that could further reduce radiation risks. Collaboration between healthcare providers, researchers, and policymakers is crucial to advancing safety standards and improving risk management strategies in medical imaging. This review highlights the importance of a comprehensive approach to managing radiation risks in medical imaging, emphasizing the need for continuous innovation, education, and policy support to protect patients, healthcare workers, and the environment.

Monte Carlo Simulation of Radioactive Elements Production in Tissues by Spallation in Cancer Therapy

Purpose: High-energy heavy ions generated by accelerators utilized in industrial and medical uses. Ar, C, and He heavy ions have been used in the treatment of cancer. In this research, it was tried to calculate the radioactive elements production in healthy tissues around tumors by heavy ions spallation process in the direct usage of high-energy ions for the treatment of cancerous tumors. Materials and Methods: The radioactive elements production in body tissues irradiated with heavy ions was calculated by Monte Carlo N Particle X-version (MCNPX) code based on the Monte Carlo method. The F8 tally card with FT8 command was utilized to derive the activation and spallation data in the range of Z1 to Z2 atomic numbers. Results: A wide range of radioactive elements was created in healthful tissues in Ne, C, Ar, and He heavy ions therapy. Results show that 10Be,14C, 26Al, 36Cl, 39Ar, 40K, 39Ar, 32Si, 22Na, and 36Cl radioactive materials were produced for high-energy heavy ions spallation in healthy soft tissue. Conclusion: The results of this research show that due to using directly high-energy ions to treat internal tumors, healthy soft tissue is activated. Also, by irradiated Ne, C, Ar, and He ions, the radioactive elements are produced with high gains and long half-lives. Therefore, in the therapy of cancerous tumors with high-energy ions, due to the production of radioactive agents, healthy tissues are at high risk.

The study on the wood candidates for the impact limiter of a spent fuel cask

The nuclear fuel transportation package is meticulously designed to enclose radioactive materials, guaranteeing containment even after undergoing a free-drop impact test and considering potential accident situations to prevent radioactive leakage. The impact limiters attached to the transport cask are engineered to absorb impact energy. Wood, renowned for its strong energy absorption capacity, is often specified as the core material within impact limiters. It is crucial to accurately determine the wood material employed in the impact limiter. This study carried out crushing experiments on various common wood materials to obtain stress versus strain data for the selection of the appropriate wood material. Indicators such as density, crushing strength, and densification strain are utilized to assess the suitability of wood as the filler material of the impact limiter. Paulownia wood is chosen based on density, the appropriate energy absorption value per unit volume, and response acceleration. The dispersity of the strengths of Paulownia wood is taken into account with the weakest-link models. The finite element method is adopted to precisely design and verify the impact limiter. The arrangement of the glulam wood is designed to balance the energy absorption in hypothetical accident conditions. Finally, tests on the application of the impact limiter in the transportation cask were conducted to validate the proper design of the impact limiter. This study can offer reference and data support for the research on wood filler materials.

Radiation shielding properties of gold nanoparticle-dispersed bismuth borate glasses using Phy-X/PSD software

With the increasing use of radioactive materials in various sectors, effective radiation shielding has become a critical concern. The present study explores the potential of bismuth borate glasses doped with gold nanoparticles for gamma-ray shielding applications. Glass samples with a base composition of 30Bi2O3:70B2O3, containing varying concentrations of 10 nm gold nanoparticles, were synthesized using the melt quenching technique. The physical and morphological properties of the samples were characterized, confirming the presence of uniformly dispersed gold nanoparticles of size (4 nm) smaller than the size of precursor nanoparticles. Shielding parameters, including mass attenuation coefficient (MAC), half value layer (HVL), ten value layer (TVL), mean free path (MFP), and effective atomic number (Zeff), were analyzed using the Phy-X/PSD program. Results showed that the obtained highest MAC value is 155.864 cm2/g which is superior to other reported materials. The HVL and TVL values increased with the increase in energy range, indicating effective gamma-ray shielding potential. These findings suggest that optimizing the dispersion and concentration of gold nanoparticles in bismuth borate glasses could enhance their performance as radiation shielding materials, making them promising candidates for various applications.

Integrating radiological technology in environmental health surveillance to enhance public safety

The integration of radiological technology into environmental health surveillance represents a significant advancement in enhancing public safety. Radiological technologies, including advanced imaging and monitoring systems, offer powerful tools for detecting and assessing environmental hazards that impact public health. This review explores the potential benefits, methodologies, and challenges associated with integrating radiological technology into environmental health surveillance. Recent advancements in radiological technology, such as high-resolution imaging systems and portable radiation detectors, have greatly improved the ability to monitor and analyze environmental radiation levels with precision. These technologies enable real-time detection of radiation exposure, providing critical data for assessing risks associated with radiation sources, such as industrial activities, nuclear power plants, and natural radioactive materials. By integrating these tools into environmental health surveillance frameworks, public health agencies can enhance their capacity to identify and address radiation-related hazards more effectively. The application of radiological technology in environmental health surveillance facilitates comprehensive monitoring of radiation levels across various environments, including urban, rural, and industrial areas. This data is crucial for identifying contamination hotspots, tracking changes in radiation levels over time, and evaluating the effectiveness of radiation control measures. Additionally, the integration of radiological technology supports the development of predictive models for assessing potential health impacts and guiding emergency response strategies in the event of radiation incidents. Despite its advantages, integrating radiological technology into environmental health surveillance presents several challenges. These include the high costs of advanced equipment, the need for specialized training for personnel, and the management of large volumes of data generated by monitoring systems. Addressing these challenges requires a coordinated approach involving government agencies, research institutions, and industry stakeholders to ensure effective implementation and sustainability. In conclusion, integrating radiological technology into environmental health surveillance has the potential to significantly enhance public safety by providing accurate and timely data on radiation exposure. Continued innovation and collaboration in this field will be essential for optimizing the benefits of radiological technology and addressing the challenges associated with its integration into environmental health monitoring systems. Keywords: Integrating; Radiological Technology; Environmental Health Surveillance; Enhance; Public Safety

Evaluating the radioactivity and health risks in oil and gas production areas: insights from Titas Gas Field, Bangladesh

ABSTRACT Conducting comprehensive studies of radioactivity and associated risk assessments in the oil and gas industry is crucial due to the potential accumulation of Naturally Occurring Radioactive Materials in production operations. This pioneering study investigates radioactivity levels in surface soil from the Titas Gas Field area in Bangladesh by a High Purity Germanium (HPGe) detector, a crucial resource of the nation’s energy infrastructure. In surface soil, the activity of 226Ra, 232Th, and 40K varied from 18–41 Bq/kg, 28–62 Bq/kg, and 280–600 Bq/kg, respectively. Particularly, the levels of 232Th exceeded the global average value for soil. These elevated 232Th levels are likely attributed to a combination of natural geological processes of enriching thorium bearing minerals, geochemical processes favouring thorium retention and human activities selectively impacting these radionuclides. The estimated of radiological risk reveals that some indices exceed recommended limits, hence pose a concern for public health. The study recommends periodic monitoring, public awareness campaigns, remediation efforts, and long-term management strategies to protect environmental and public health. The findings of this research underscore the critical need to recognise and address radiological hazards associated with gas extraction activities to safeguard the health and safety of workers and nearby communities in Bangladesh.

Identification of Distorted Gamma-Ray Signature Patterns Using Digital Filtering and Auto-Associative Memory Implemented with a Hopfield Neural Network

The detection and identification of radioactive sources in search applications involve analyzing passive gamma-ray emissions from high-level radioactive materials. This process uses a mobile detector-spectrometer in a complex field test environment. Recently, the use of artificial intelligence for gamma-ray spectrum analysis has shown promising results. However, challenges persist in identifying isotopic signatures from spectral measurements that may be distorted due to source shielding, random variations in natural radioactive background, or insufficient measurement time to obtain clear spectral lines. This paper presents a novel intelligent signature recognition method that combines digital filtering techniques with an artificial Hopfield Neural Network (HNN). The HNN leverages auto-associative memory to store training sample patterns and match them with incoming gamma spectra from distorted sources. It restores the testing sources’ measurements by finding the closest matching signature patterns in the spectral library. Before HNN recognition, the measured spectrum undergoes preprocessing with a digital image filter to reduce fluctuations. Performance of the proposed method is evaluated using a set of gamma-ray spectra measured with a sodium iodide detector. The data collected include measurements from six pure samples: 241Am, 60Co, 137Cs, 192Ir, 239Pu, and 235U, which are used for training and validation (i.e. six cases). Additionally, the data set contains 24 distorted synthesized sources with various fluctuating backgrounds. Test results demonstrate the potential of the proposed method to accurately recognize the correct isotope with high precision, achieving an accuracy rate exceeding 85%. Furthermore, the proposed method exhibits superior performance compared to the conventional multiple regression fitting and simple feedforward neural network methods.

Tunable sulfur vacancies in amorphous-crystalline AC-Bi2S3-x@C derived from CAU-17 for efficient capture of radioiodine: Comparison of sulfur vacancies in amorphous and crystalline structures

Solid-phase adsorption has been recognized as an effective method for the control of volatile radioactive iodine in spent fuel reprocessing plant off-gases. However, it is still a challenge to develop efficient and stable iodine capture adsorbents. In this work, sulfur-vacancy-rich amorphous-crystalline AC-Bi2S3-x@C was prepared by solvothermal vulcanization using CAU-17 as a precursor. Based on the synergistic effect of the amorphous structure and sulfur vacancy defects, AC-Bi2S3-x@C exhibited fast adsorption equilibrium time (15 min), distinguished iodine adsorption capacity (1763.9 mg g−1), high percentage of chemical adsorption (93.4 %) as well as favorable thermal and irradiation stability. Adsorption experiments and theoretical calculations verified that the amorphous structure not only enhance the charge transfer between sulfur vacancy defects and iodine molecules, but also offers rapid diffusion channels for iodine molecules to the interior of the adsorbent and sufficient internal binding sites to promote iodine molecule adsorption in its interior. The used adsorbent showed high iodine retention (92.3 %) and excellent chemical durability (normalized iodine leaching rate of 4.63 × 10-5 g m−2 d-1) in glass solidification. In general, this work presented a new concept in the design and synthesis of efficient radioactive iodine capture materials.

Numerical study for atmospheric transport of radioactive materials for hypothetical severe nuclear accident under different meteorological conditions

A study for atmospheric transport is essential for the consequence assessment of severe nuclear accidents since radionuclides could be released from the nuclear facility into the atmosphere and cause radioactive pollution in the environment. Atmospheric transport behaviors are strongly related with meteorological conditions, which can obviously influence the transport and diffusion characteristics of radioactive materials in the atmosphere; thus, it is meaningful to investigate the coupling effects between meteorological processes and transport behaviors of radioactive materials. To evaluate the influence of meteorological conditions on atmospheric transport, meteorological parameters for different seasons were first acquired by the weather research forecast model. Furthermore, atmospheric transport behaviors of radioactive materials were simulated by the meso-scale numerical model under different meteorological conditions, and numerical analyses were conducted toward transport and deposition behaviors of radioactive materials. In addition, the influence of FDDA (four-dimensional data assimilation) on meteorological parameters and atmospheric transport behaviors was researched. The present study is important for strengthening consequence assessment for severe nuclear accident and made it possible to apply the data assimilation technology in further research works.

Development and Experimental Validation of a Heat Transfer Model for Spilled Molten Salt Pools

A spill of radionuclide-bearing molten salt is one of the major postulated events that needs to be analyzed for liquid fluorine salt–cooled high-temperature reactor (FHR) or molten salt reactor licensing purposes. In this postulated event, radioactive source term materials (RSTMs) in the molten salt are discharged from the reactor vessel to the reactor building. The release of RSTMs from the spilled salt pool to the gas space in the reactor building is expected to be controlled by the cooling behavior of the spilled salt, including the growth and shrinkage of the solid crust on the surface of the spilled salt pool. This paper presents a simulation model for spilled salt pool heat transfer and validation efforts. The validation data come from two molten salt spill tests that were performed recently: the PELE2 test by the Rapid Experimental Laboratory of Kairos Power LLC (KP) and the Argonne salt cooling test conducted by Argonne National Laboratory. The former was a large-scale test involving kilograms of molten spilled FLiNaK salt, and the latter was a relatively smaller-scale test targeting various processes associated with a salt spill event. Both tests generated valuable data sets that can be used to assess salt cooling and validate evaluation models. This paper provides a new one-dimensional model that can simulate the cooling process of a spilled salt pool as well as the thermal responses of heat structures, such as the stainless steel liner and the concrete below the salt. The model has been implemented as part of KP-SAM code, which is a branch of the systems code SAM specific to KP FHR. The simulation results of the model are compared with the data of the PELE2 and Argonne tests, and reasonable agreements are observed between the model and test data.

Determination of Excessive Lifetime Cancer Risk for Workers Exposed to Natural Radioactive Materials in Various Equipment in Oil and Gas Sector

In the oil and gas sector of Basrah, natural radioactive materials are accumulated in various equipment like wellheads, pumps, and separation vessels, often manifested as scales, sludge, and other forms of waste. Without proper preventive measures, these accumulations pose significant risks to workers, the public, and the environment. This study aims to assess the lifelong cancer risks associated with production processes and the handling of resultant waste, be it scale sediments, sludge, or soil. Sample collection across different regions was based on the evaluation of production and storage facilities. Using a high-purity germanium detector (HPGe), activity concentrations of 226Ra, 232Th, and 40K were measured. These concentrations were then used with standard equations to determine indoor effective dose rates. The regional-weighted (the lifetime risk of cancer is a measure of the cumulative risk of cancer over a specific age range and has a clear, intuitive appear) average of the lifetime excessive cancer risk was varied between (0.40 to 0.11 ×10-3) for ELCRoutdoor, (3.13 to 0.86 ×10-3) for ELCRindoor and (0.97 to 3 ×10-3) for ELCRtotal, significantly surpassing the global average value of (0.29x10-3). This disparity underscores the heightened risk posed by these activities, emphasizing the urgent need for enhanced safety measures and regulatory oversight to safeguard human health and the environment.

Assessing Radiation Fallout in Public Zones near the Nevada National Security Site (NNSS): A Recent Study.

A comprehensive radiological study was conducted in the surrounding public zones of the Nevada National Security Site to identify traces of resuspended radioactivity and heavy elemental contamination that might have resulted from various activities. The study used passive and active nuclear methods, specifically gamma spectrometry and instrumental neutron activation analysis, respectively. Passive gamma spectra analysis of air filter papers from various Community Environmental Monitoring Program stations conclusively verified the presence of radionuclides exclusively originating from the natural decay series of 238U and 232Th. Furthermore, gamma spectrometry and instrumental neutron activation analysis of plant samples from surrounding areas of the Nevada National Security Site revealed the absence of any unusual elemental contamination in the environment. These results demonstrated that there was no measurable radiological impact on the public zones surrounding the site resulting from the spread of radioactive materials or toxic heavy metals associated with previous or ongoing activities at Nevada National Security Site. Therefore, the safety of public zones concerning retained radioactivity and harmful elemental contamination arising from Nevada National Security Site operations is negligible. The significance of this study is further pronounced in the current geopolitical context, as it establishes the baseline elemental composition for various desert plants for future reference.