Radioactivity Concentration Research Articles

Investigating radiation profiles and conducting risk assessment for ecological and environmental components on Vaan and Koswari islands in the Tuticorin group of islands, India.

Natural radioactive concentration assessment was conducted on sediment, water, and biota obtained on Vaan and Koswari islands in the Tuticorin group of islands, Tamil Nadu, India. For biotic and abiotic components, radiation profiles such as gross alpha, beta, primordial radionuclide, polonium, and lead analyses were performed. The gross α and β range from BDL to 15.18 ± 1.7Bq/kg and 40.43 ± 4.9Bq/kg to 105.12 ± 11.7Bq/kg, respectively. Primordial radionuclides were analyzed using Nal(TI)-based scintillator with PC-MCA, and the concentrations ranged from 13.43 ± 3.3Bq/kg to 30.97 ± 9.6Bq/kg with a mean of 21.31 ± 2.7Bq/kg for 238U; for 232Th, the values ranged from 11.09 ± 2.6Bq/kg to 33.55 ± 9.5Bq/kg with an average value of 23.89 ± 3.7Bq/kg; and for 40K, the values are 93.33 ± 27.3Bq/kg to 219.91 ± 39.6Bq/kg with an average value of 148.27 ± 21.7Bq/kg. The present study values are lesser than the world average values. 210Po and 210Pb concentrations with an average value were determined to be 33.13Bq/L and 16.56Bq/L, 47.55Bq/L and 22.37Bq/L in the water sample, and 50.437Bq kg1 and 62.012Bq kg1, 46.99Bq/kg and 58.625Bq/kg in sediments of Vaan island and Koswari island. The concentrations of 210Po and 210Pb of Pogonias cromis were 19.27 ± 1.5Bq/kg and 8.27 ± 1.01Bq/kg, Belonidae 28.54 ± 2.4Bq/kg and 18.32 ± 2.3Bq/kg, Lepisosteidae 18.68 ± 1.4Bq/kg and 11.17 ± 1.8Bq/kg. The committed effective dosage was determined to be 35.74-54.61 µSv/y for 210Po and 25.39-56.25 µSv/y for 210Pb, in which the 210Pb value is lower; however, the 210Po value is higher than the global average value. The annual committed effective dosage as well as the radiological hazard indices were assessed and found to be much below the global average and the recommended limit, respectively. This research provides an extensive analysis of natural background radiation and establishes a baseline report on the radiological profile of biotic and abiotic factors in the Tuticorin group of islands, namely Vaan and Koswari, in Tamil Nadu, India.

Feasibility of Treatment Agents in Radioactive Iodine Separation from Waste Liquids.

To discharge waste liquid containing radioactive iodine into sewage systems, long-term storage or dilution with a large amount of water may be required until the radioactivity concentration reduces below the standard value. Processing the waste liquid could be easier if radioactive iodine could be separated from the water. This study verified the effectiveness of superabsorbent polymer and α-cyclodextrin as treatment agents to separate radioactive iodine from waste liquids. Sodium iodide (Na 125 I) was added to purified water and artificial urine to prepare simulated waste liquids containing iodine equivalent to the urine of patients treated with radioactive iodine. The as-prepared simulated waste liquid was poured into a container with superabsorbent polymer and left for 90 d. The residual iodine rate in the simulated waste liquid was estimated by measuring 125 I radioactivity. When the water was sufficiently dried, residual iodine rates on day 15 were 0.102 and 0.884 in the simulated waste liquids comprising purified water and artificial urine, respectively. The simulated waste liquid comprising purified water with 5% α-cyclodextrin absorbed by 1 g of superabsorbent polymer had a residual rate of 0.980. Moreover, the residual rate of simulated waste liquid comprising artificial urine with 2% α-cyclodextrin absorbed by 1 g of SAP was 0.949. Superabsorbent polymer combined with α-cyclodextrin was an effective treatment agent for separating radioactive iodine from waste liquids.

Negligible radiological impact of Indian nuclear power plants on the environment and the public: Findings from a 20-year study

Nuclear power plants, recognized for their extended operational life, minimal greenhouse gas emissions, and high-power density, are deemed as reliable energy sources. Nonetheless, concerns persist regarding the radioactive discharges from these plants and their potential impact on health and the environment. To comprehend the radiological implications of such releases, this study presents, for the first time, an analysis of radiological data from 7 Indian nuclear power plants (NPPs), collected by Indian environmental survey laboratories (ESL) over the past two decades (2000-2020). This dataset encompasses radioactivity concentrations in the atmospheric, aquatic, and terrestrial environments within a 30 km radius of each NPP, as well as the annual cumulative external gamma doses recorded by environmental thermoluminescence dosimeters (TLDs). The analysis yielded several key findings: (i) Radioactivity concentrations around the NPPs were low and comparable to values measured at other nuclear power plant sites worldwide; (ii) Tritium concentrations in receiving water bodies were <1 % of the internationally recommended limit of 10,000 Bq/l; (iii) The estimated total radiation doses to the public were at most 10 % of the stipulated regulatory dose limit of 1000 μSv and consistently decreased over the study period and (iv) Variations in doses among the NPP sites were primarily attributed to legacy technology used in specific reactors. These results indicate efficient and secure reactor operations and the minimal contribution of Indian nuclear power plants to anthropogenic doses in the country. The findings hold potential significance for reinforcing India's commitment to advancing its nuclear power program.

The determination of the optimal threshold on measurement of thyroid volume using quantitative SPECT/CT for Graves' hyperthyroidism

PurposeTo investigate the optimal threshold for measuring thyroid volume in patients with Grave's hyperthyroidism (GH) by SPECT/CT.Materials and methodsA 53 mL butterfly-shaped hollow container made of two 45-degree transparent elbows was put into a NEMA IEC phantom tank. The butterfly-shaped container and the tank were then filled with Na99mTcO4 of different radioactive concentrations, respectively, which could simulate thyroid gland with GH by different target-to-background ratios (T/B) (200:1, 600:1, 1000:1). The different T/B of planar imaging and SPECT/CT were acquired by a Discovery NM/CT 670 Pro SPECT/CT. With Thyroid software (Version 4.0) of GE-Xeleris workstation, the region of the thyroid gland in planar imaging was delineated. The thyroid area and average long diameter of both lobes were substituted into the Allen formula to calculate the thyroid volume. The calculation error was compared with the actual volume. Q-Metrix software was used to perform CT-based attenuation correction, scatter correction, resolution recovery. Ordered-subsets expectation maximization was used to reconstruct SPECT data. 20%, 25%, 30%, 40%, 50%, 60% thresholds were selected to automatically delineate the volume of interest and compared with the real volume, which determinated the optimal threshold. We measured the thyroid volume of 40 GH patients using the threshold and compared the volumes obtained by planar imaging and ultrasound three-dimensional. The differences of the volumes with different T/B and thresholds were compared by the ANOVA and least significant difference t test. The volumes delineated by SPECT/CT were evaluated using ANOVA, least significant difference t test, correlation analysis and, linear regression and Bland–Altman concordance test plot. The differences and consistency of thyroid volume were compared among the above three methods.ResultsThere was no significant difference in the results between different T/B models (P > 0.05). The thyroid volume calculated by the planar imaging formula method was higher than the real volume, with an average overestimation of 22.81%. The volumes delineated by SPECT/CT threshold automatically decreased while the threshold increased. There were significant differences between groups with different thresholds (P < 0.001). With an average error of 3.73%, the thyroid volume analyzed by the threshold of 25% was close to the results of ultrasound measurement (P > 0.05). Thyroid volume measured by planar imaging method was significantly higher than ultrasound and SPECT/CT threshold automatic delineation method (P < 0.05). The agreement between the SPECT/CT 25% threshold and ultrasound (r = 0.956, b = 0.961) was better than that between the planar imaging and ultrasound (r = 0.590, b = 0.574). The Bland–Altman plot also showed that the thyroid volume measured by the 25% threshold automatic delineation method was in good agreement with the ultrasound measurement.ConclusionsThe T/B has no effect on the measurement of thyroid volume in GH patients; planar imaging method can significantly overestimate thyroid volume in GH patients, and 25% threshold automatic delineation method can obtain more accurate thyroid volume in GH patients.

Automating the production of [Fe18FF2(BnMe2-tacn)] and investigating radiostabilisers for use with high-activity [18F]F−

Abstract The manual radiofluorination and purification of [FeF3(BnMe2-tacn)] (tacn = 1,4,7-triazacyclononane) using 18F− in aqueous EtOH has been translated to a GE FASTLab™ automatic synthesis platform and optimised by conducting a series of low-activity radiolabelling experiments to explore the effects of varying the precursor concentration, temperature, heating time, addition of NaOAc buffer and EtOH:H2O ratio. The optimal conditions were determined to be 1 mg/mL of the precursor being heated at 120 °C for 10 min in 75 %:25 % EtOH:H2O containing 18F−, with elution using 10 mM NaOAc, giving 61 % radiochemical yield (RCY). These conditions were then employed with high-activity 18F− giving a 97 % radiochemical purity (RCP) at t = 0, which decreases by 22 % over 5 h. Sodium ascorbate, nicotinamide and p-benzoic acid (pABA) were then tested as potential radiostabilisers for this system, initially using low-activity 18F−. These experiments revealed very rapid defluorination of the radioproduct in the presence of sodium ascorbate. In contrast, both nicotinamide and pABA appear to be effective radiostabilisers, resulting in RCP values of 91 % and 89 %, respectively, after 2 h, which compare with an RCP of 81 % under analogous conditions at t = 2 h in their absence. High-activity experiments were then undertaken with addition of 5 mg/mL of nicotinamide, with a radio-active concentration (RAC) of 220 MBq/mL, giving RCY of 26 % and following purification, RCP values for the [Fe18FF2(BnMe2-tacn)] product of 97 % at t = 0 and 86 % after 3 h.

Environmental Radioactivity, Ecotoxicology (238U, 232Th and 40K) and Potentially Toxic Elements in Water and Sediments from North Africa Dams

The natural radioactivity of 238U, 232Th and 40K was measured in water and sediment samples collected from Sidi Salem dam (Tunisia) and Aïn Dalia dam (Algeria) in the Tuniso-Algerian transboundary basin. The samples were measured using a TERRA detector of gamma, beta, and alpha rays, and atomic absorption and gamma-ray spectrometry were used to analyze the levels of radionuclides and toxic elements, respectively. Potentially toxic elements (Fe, Pb, Zn, Ni, Cr, Cu and Cd) and associated health risks in surface water and sediment of dams were investigated in this present study. The concentrations of Fe, Pb, Zn, Ni, Cr, Cu and Cd in surface water ranged from 5.430 to 9.700 mg·L−1, 0.022 to 0.168, 0.018 to 0.142, 0.065 to 0.366, BDL to 0.0351, BDL to 0.071 and BDL to 0.048 mg·L−1, respectively. In the sediments, the concentrations of Fe, Pb, Zn, Cu, Ni, Cd and Cr were of the order of 136.7, 3.41, 3.22, 0.213, 0.182, 0.15 mg·L−1 and BDL, respectively. The mean radioactivity rates in the water samples were 1.72, 0.068 and 94.6 Bq·L−1 for 238U, 232Th and 40K, respectively (Tunisia dam), and were 1.9, 0.09 and 131.43 Bq·L−1 for 238U, 232Th and 40K, respectively (Algeria dam). The mean 238U, 232Th and 40K radioactivity concentrations measured in the sediment samples were 2.67, 0.18 and 197.87 Bq·kg−1, respectively (Tunisian dam), and were 4.34, 0.27 and 287.61 Bq·kg−1, respectively (Algeria dam). The activity concentration of 40K was higher than that of 238U and 232Th for the water and sediment samples. The activity concentrations follow the order 40K &gt; 238U &gt; 232Th. The cumulative impact of these radio-geochemical elements can cause immediate serious problems in the ecosystem due to their high potential toxicity to the environment and human health in this study area and can be transposable to any other similar region. A good knowledge of monitoring quality and quantity for transboundary water resources and international collaborations are essential to safeguard human health (women’s breast cancer, thyroid cancer, neurological impact) and avoid conflicts, especially during climatic upheavals of drought.

Fractionation of environmental radioactivity in road dust from a megacity: external and internal health risks.

Naturally occurring radioactive materials (NORMs: 232Th, 226Ra, 40K) can reach our respiratory system by breathing of road dust which can cause severe health risks. Targeting the pioneering consideration of health risks from the NORMs in road dust, this work reveals the radioactivity abundances of NORMs in road dust from a megacity (Dhaka) of a developing country (Bangladesh). Bulk chemical compositions of U, Th, and K obtained from neutron activation analysis were converted to the equivalent radioactivities. Radioactivity concentrations of 226Ra, 232Th, and 40K in road dust ranged from 60-106, 110-159, and 488-709Bqkg-1 with an average of 84.4 ± 13.1, 126 ± 11, and 549 ± 48Bqkg-1, respectively. Estimated 226Ra, 232Th, and 40K radioactivities were, respectively, 1.7-3.0-, 3.7-5.3-, and 1.2-1.8-folds greater than the affiliated world average values. Mechanistic pathway of NORMs' enrichment and fractionation relative to the major origin (pedosphere) were evaluated concerning the water logging, relative solubility-controlled leaching and translocation, climatic conditions, and aerodynamic fractionations (dry and wet atmospheric depositions). Computation of customary radiological risk indices invokes health risks. Noticing the ingress of NOMR-holding dust into the human respiratory system along with the associated ionizing radiations, the computed radiological indices represent only the least probable health hazards. Nevertheless, in real situations, α-particles from the radioactive decay products of 232Th and 238U can create acute radiation damages of respiratory system. Policymakers should emphasize on limiting the dust particle evolution, and public awareness is required to alleviate the health risks.

Radioactivity concentration and risk indices in intertidal sediments of the Red River Delta, Vietnam

Radioactivity concentration and risk indices in intertidal sediments of the Red River Delta, Vietnam

Quantitative evaluation of radioactive cesium concentration in leachate and landfill waste at a municipal waste final disposal site in Fukushima prefecture

Quantitative evaluation of radioactive cesium concentration in leachate and landfill waste at a municipal waste final disposal site in Fukushima prefecture

Evaluation of Radioactivity Contents and Excess Lifetime Cancer Risk Due to Ingestion from Natural Radionuclides in Maize Samples from Some Selected Maize Farms in Ekiti State, Nigeria

The study was carried out to evaluate the radioactivity concentrations of 40K, 232Th and 238U in five maize samples collected from maize farms within Ekiti State, Nigeria. The activity concentration measurements were determined using n – type co-axial HPGe detectors for the state. The activity concentrations were found to vary from 994.67 – 2457.01 Bq Kg-1 for 40K, 32.84 – 91.88 Bq kg-1 for 232Th and 43.21 – 97.77 Bq kg-1 for 238U respectively. The annual effective dose to individuals from the consumption of the Maize was estimated on the basis of the measured radionuclides content in the food crop which ranged between 0.41 and 1.51 m Svy-1 respectively. The value1.04 m Svy-1 were obtained for the state as the mean total annual effective dose. The mean excess life time cancer risk was also calculated to be 2.06x10-9 . The value was compared with the internationally acceptable limits and found to be far less to the maximum permissible dose of 1.0 x10-3 recommended for the public by the United Nations Scientific Committee on the Effects of Atomic Radiation. Hence, the maize was found to be safe for human consumption.

Impact of Different Acquisition Modes on Image Quality and Quantitative Accuracy for Bone SPECT Using Ordered Subset Conjugate-gradient Minimizer

We evaluated the effect of different xSPECT Bone acquisition methods on image quality and quantitative accuracy. A mixed bone-equivalent solution set to 250 HU and 99mTc was filled with the SIM2 Bone phantom. The xSPECT Bone acquisitions were performed with the step and shoot (SS) mode and two continuous modes (continuousview, continuoustotal) of the times per view, and the total acquisition times were the same as the SS mode. The radioactive concentration ratio of normal bone and tumor was set to 1 : 6. The reconstructed images were evaluated using uniformity, contrast, spatial resolution, recovery coefficient (RC) of the tumor part, and detectability. The detectability score (DS), an overall evaluation of detectability, was calculated from the results of uniformity and contrast. Uniformity of SS, continuousview, and continuoustotal methods was 29.4%, 17.4%, and 11.1%, respectively. Spatial resolution, RC, and detectability were similar among the SS mode and two continuous modes; however, the continuous modes showed good uniformity and contrast compared with the SS mode. In addition, the detectability of the continuous mode was equal to or superior to that of the SS mode.

ASSESSMENT OF KARAMUSTAFA GOLD-BEARING Zn-Pb MINE (GÜMÜŞHANE, TÜRKİYE) AREA IN TERMS OF NATURAL AND ARTIFICIAL RADIOACTIVITY

This study aimed to assess the environmental effects of natural and artificial radioactivity contents, especially in the context of medical geology of base metal-containing mineral deposits. In the study, artificial/anthropogenic (137Cs) and natural (226Ra, 232Th and 40K) radioactivity levels in the soil of the Karamustafa gold-bearing Zn-Pb-(±Cu) mining area, one of the important mines of Gümüşhane (NE Türkiye), were determined and evaluated. In order to determine the natural and artificial radioactivity of the mining area, 9 soil samples were collected from different parts of the field, taking into account the geological and alteration characteristics of the field. 232Th, 226Ra and 40K activities of the samples prepared according to the relevant laboratory procedures were determined by the gamma-ray spectrometry, and the artificial radioactivity values of 137Cs were also measured. As a result of the study, it was determined that the 40K and 226Ra average activities of the Karamustafa gold-bearing Zn-Pb-(±Cu) mining area exceeded the world averages in most sampling points, while the 232Th activities were above the world averages at some sampling points. It has been determined that the artificial/human-derived 137Cs radioisotope values in the field are remarkably high. Considering the major radio indices calculated for the field, it was determined that the absorbed dose rate and annual effective dose rate indices of the mine site exceeded the relevant threshold values. When all the data obtained from the field were evaluated together, it was concluded that the mine field needed detailed study in the context of radiation risk.

A Preliminary Study on Evaluation of Time-Dependent Radionuclide Removal Performance Using Artificial Intelligence for Biological Adsorbents

Background: Recently, biological adsorbents have been developed for removing radionuclides from radioactive liquid waste due to their high selectivity, eco-friendliness, and renewability. However, since they can be damaged by radiation in radioactive waste, a method for estimating the bio-adsorbent performance as a time should consider the radiation damages in terms of their renewability. This paper aims to develop a simulation method that applies a deep learning technique to rapidly and accurately estimate the adsorption performance of bio-adsorbents when inserted into liquid radioactive waste.Materials and Methods: A model that describes various interactions between a bio-adsorbent and liquid has been constructed using numerical methods to estimate the adsorption capacity of the bio-adsorbent. To generate datasets for machine learning, Monte Carlo N-Particle (MCNP) simulations were conducted while considering radioactive concentrations in the adsorbent column.Results and Discussion: Compared with the result of the conventional method, the proposed method indicates that the accuracy is in good agreement, within 0.99% and 0.06% for the R&lt;sup&gt;2&lt;/sup&gt; score and mean absolute percentage error, respectively. Furthermore, the estimation speed is improved by over 30 times.Conclusion: Note that an artificial neural network can rapidly and accurately estimate the survival rate of a bio-adsorbent from radiation ionization compared with the MCNP simulation and can determine if the bio-adsorbents are reusable.

Development of a Methodology for Estimating Radioactivity Concentration of NORM Scale in Scrap Pipes Based on MCNP Simulation

Development of a Methodology for Estimating Radioactivity Concentration of NORM Scale in Scrap Pipes Based on MCNP Simulation

Detectability of cold tumors by xSPECT bone technology compared with hot tumors: a supine phantom study.

Detecting cold as well as hot tumors is vital for interpreting bone tumors on single-photon emission computed tomography (SPECT) images. This study aimed to visually and quantitatively demonstrate the detectability of cold tumors using xSPECT technology compared with that of hot tumors in the phantom study. Five tumors of different sizes and normal bone contained a mixture of 99mTc and K2HPO4 in a spine phantom. We acquired SPECT data using an xSPECT protocol and transverse images were reconstructed using xSPECT Bone (xB) and xSPECT Quant (xQ). Mean standardized uptake values (SUVmean) in volumes of interest (VOI) were calculated. Recovery coefficients (RCs) for each tumor site were calculated with reference to radioactive concentrations. The SUVmeans of the whole vertebral body for hot tumor bone image in cortical bone phantom reconstructed by with xB and xQ were 5.77 and 4.86 respectively. The SUVmean of xB was similar to the true value. The SUVmeans for xB and xQ reconstructed images of cold tumors were both approximately 0.16. The RC of the cold tumor on xQ images increased as the tumor diameter decreased, whereas that of xB remained almost constant regardless of the tumor diameter. In conclusion, the quantitative accuracy of detecting hot and cold tumors was higher in the xB image than in the xQ image. Moreover, the visual detectability of cold tumors was also excellent in xB images.

Novel environmental monitoring detector for discriminating fallout and airborne radioactivity

Early warning networks are used for detecting abnormal radioactivity levels in the environment. State-of-the-art networks are equipped with both dose rate detectors and spectrometric stations. Current networks don’t automatically discriminate between radioactivity on the ground and in the air. A novel directional sensing gamma radiation detector utilizing a collimated phoswich scintillator was developed. The signals from the two scintillator materials are separated using a pulse shape discrimination. The separated signals are employed to determine the radioactivity concentrations on the ground and in the air assuming specific concentration distributions. Limitations related to imperfect directional sensing and dead time are discussed.

IMPACT OF LEGISLATIVE CHANGE ON THE CLASSIFICATION OF RAW MATERIALS AND BUILDING MATERIALS IN TERMS OF NATURAL RADIOACTIVITY

Natural radioactivity is present in the human environment to a greater or lesser extent, also in varioustypes of raw or building materials. Monitoring of the concentration of natural radioactive isotopesof potassium 40K, radium 226Ra and thorium 228Th or 232Th in samples of raw and/or constructionmaterials allows assessing the exposure of people to ionizing radiation emitted by these materials.Exceeding the limit value of the radioactive concentration index for raw and/or building materials,defined in the Ordinance of the Council of Ministers (Polish Journal of Laws/Dz.U. No. 33/2021),may result in an effective radiation dose greater than 1 mSv/year – the dose limit for the population.In Poland, pertinent legislation requiring the establishing of the natural radioactivity of raw and/orbuilding materials dates back to the 1970s and has been changed several times by now. However, themost significant changes in the legislation have occurred recently. Due to the obligation of imposingthe application of the provisions of the of European Council 2013/59/EURATOM of 5 December2013 laying down basic safety standards for protection against risks arising from exposure to theeffects of ionizing and repealing Directives 89/618/Euratom, 90/641/ Euratom, 96/29/Euratom,97/43/Euratom and 2003/122/Euratom (the so-called BSS version), it was necessary to adopt theamendment to the Atomic Law. The implementation of the BSS Directive in Poland was issued on thebasis of the resolution of the Parliament of June 13, 2019 amending the Atomic Law Act and the FireProtection Act (Polish Journal of Laws/Dz.U. 2019, item 1593). The amendment of the Atomic LawActs led to the harmonisation of regulations on radioactivity in raw and building materials betweenPoland and the Member States. This article presents the impact of an amendment of the AtomicLaw and of the accompanying normative acts on the studies of the natural radioactivity of raw andconstruction materials, using the example of an analysis of the concentration of natural radioactiveisotopes present in the coal combustion products (CCP), i.e. fly ash, slags and ash-slag mixtures.

Production and synthesis of a novel 191Pt-labeled platinum complex and evaluation of its biodistribution in healthy mice

We previously reported that our sugar-conjugated platinum complex (cis-dichloro [(2-fluoro-α-d-glucopylanosidyl) propane-1,3-diamine] platinum: FGC-Pt) has low toxicity and tumor growth inhibitory effect comparable to that of cisplatin. We focused on radioactive Pt isotopes in order to analyze the kinetics of FGC-Pt using gamma-ray imaging techniques, assuming that FGC-Pt could be used for chemotherapy in the future. Therefore, in this study, we aimed to develop a non-invasive method to analyze the biodistribution of FGC-Pt using 191Pt-labeled FGC-Pt ([191Pt]FGC-Pt).191Pt was produced via the (n,2n) reaction induced by accelerator neutrons. [191Pt]FGC-Pt was prepared using two different methods. In the first method, [191Pt]FGC-Pt (method A) was obtained through the accelerator neutron irradiation of FGC-Pt. In the second method, [191Pt]FGC-Pt (method B) was synthesized using [191Pt]K2PtCl4, which was obtained by the accelerator neutron irradiation of K2PtCl4. Highly purified [191Pt]FGC-Pt was obtained using the latter method, which suggests that the synthetic method using a 191Pt-labeled platinum reagent is suitable for the radioactivation of platinum complexes.We also aimed to investigate whether a significant correlation existed between the biodistribution of FGC-Pt and [191Pt]FGC-Pt in healthy mice 24 h after tail vein administration. FGC-Pt and [191Pt]FGC-Pt were similarly distributed in healthy mice, with a higher accumulation in the liver and kidney 24 h post injection. In addition, a significant correlation (p < 0.05, r = 0.92) between the 191Pt radioactivity concentration (%ID/g (gamma counter)) and platinum concentration (%ID/g (ICP-MS)) was observed in 13 organs. These results suggest that 191Pt-labeled compounds, synthesized using radioactive platinum reagents, can be used to confirm the biodistribution of platinum compounds. Our study on the biodistribution of [191Pt]FGC-Pt is expected to contribute to the development of novel platinum-based drugs in the future.

Evaluation of Chemical and Impacts of Radionuclides in Borehole Waters in Igbajo Town, Osun State, Nigeria

Water is a universal solvent on earth and sources such as wells, rivers, springs, boreholes, and other freshwater bodies typically serve as a pathway for contaminants to enter the ecosystem while also supplying water for domestic and drinking purposes. The activity concentrations of radionuclides in borehole water in Igbajo town were assessed using gamma-ray spectroscopy, so as to effectively determine the degree of radiological risk to the environment and its inhabitants, the outcomes were used to calculate all the radiological impact parameters. The activity concentrations obtained for 40K, 238U and 232Thranged from 7.25±0.60 to 62.15±4.48Bq.L–1; 3.08±0.45 to 15.24±3.07 Bq.L–1and 1.08±1.10 to 17.75±1.59 Bq.L–1 and with average values of 23.12±1.59 Bq.L–1, 6.27±2.01 Bq.L–1 and 7.01±0.89 Bq.L–1 respectively. The Annual Effective Dose (AED) for ingested radionuclide in drinking water for an adult was1.4872 μSv.yr–1. The Radium Equivalent Activity Index, Raeq obtained was 34.9186 Bq.L–1. The estimated hazard indices Hint and Hext were 0.04876 and 0.06574 respectively. The Excess Lifetime Cancer Risk, ELCR (x10–6) was 5205.15. With a lifetime expectancy of 70 years, this high value suggests that there is a high chance of developing cancer.The value of the Annual Gonadal Equivalent Dose, AGED in the water was 55.9175μSv.yr–1. The estimated Gamma Index, Iγ was0.1273 mSv.yr–1. There is a significant health hazard to the environment and people living in the area owing to the radioactivity contents and radiological impact parameters. Hence, the need for urgent attention and means to prevent hazards which the overdose could cause.

Phase I/IIa trial of 18F-prostate specific membrane antigen (PSMA) 1007 PET/CT in healthy volunteers and prostate cancer patients.

18F-PSMA 1007 is a promising PET tracer for prostate cancer. We aimed to examine the safety, biodistribution, radiation dosimetry, and clinical effectiveness in Japanese healthy volunteers and patients with prostate cancer. Part A evaluated the pharmacokinetics and exposure doses in three healthy volunteers. Part B evaluated the diagnostic accuracy in patients with untreated preoperative prostate cancer (Cohort 1, n=7) and patients with biochemical recurrence (Cohort 2, n=3). All subjects received a single dose of 3.7MBq/kg 18F-PSMA 1007. Results: 18F-PSMA 1007 was found to be safe and well tolerated in all subjects. No serous AEs or drug-related AEs were identified during the present study. The average blood radioactivity concentration reached a maximum of 47.87±1.05 (percentage of injected dose [%ID]/ml) at 5min and then decreased to 1.60±0.78 in 6h. The systemic radioactivity reached a maximum of 211.05±6.77 (%ID$\times$103) at 5min and decreased to 7.18±3.91 in 6h. The sensitivity and positive predictive value were 100% and 100% based on both pathologic and imaging confirmation as gold standard. In Cohort 1, 15 primary foci (11.9%) were >5mm in the largest diameter and identified in 39 of 126 segments (30.1%). The sensitivity, specificity, positive predictive value, negative predictive value, and accuracy for 60min uptake time acquisition were 80.0, 96.5, 91.4, 91.2 and 91.3%, respectively. Our study revealed that 18F-PSMA 1007 was safe, well tolerated and showed high accuracy in the diagnosis of prostate cancer.