Radionuclide Measurements Research Articles

Transfer of Metals Relevant to the Nuclear Fuel Cycle into Lumbriculus variegatus from Boreal Freshwater Sediments

Radioecological modeling requires information about the transfer of different elements and their radionuclides. These models have traditionally used radionuclide concentrations in water to predict concentrations in aquatic organisms. In addition, these models often assume this accumulation to be linear. In this study, we investigated the transfer of Ba, Co, Ni, Sr, U, and Zn from sediment and artificial freshwater to laboratory-reared benthic Oligochaeta (Lumbriculus variegatus). Total elemental concentrations were used as substitute measurements for specific radionuclides. The radioactive isotopes of these metals are an important part of the nuclear fuel cycle. During various parts of this cycle, they can end up in aquatic environments, mostly at low concentrations. Sediment samples were collected from three small lakes connected to a former uranium mine in Eastern Finland, as well as from a reference lake from a different drainage area nearby. A 28-day bioaccumulation experiment was conducted using collected samples and artificial freshwater. Concentrations measured from sediment, porewater, overlying water, and L. variegatus indicated importance of sediment as a source of uptake for all tested metals. Linear accumulation assumption (constant concentration ratio) also did not appear to be correct for most metals. Metal uptake by L. variegatus seemed to reduce at higher sediment concentrations for most metals, except for Ba and Co. Thus, the common assumptions related to radioecological modeling were not supported by our findings for majority of tested metals and accumulation sources. Further basic research is required to develop more accurate and robust radioecological models.

Measurement of Radionuclides and their Impact on the Environment Around Asphalt Plants in Delta State

Measurement of radionuclides and their impact on the environment around asphalt plants in some selected Asphalt mixing plant within Delta State, Nigeria was carried out. The Background Ionizing Radiation and the GPS of the location was measured using a well calibrated Gamma scout; Geiger counter multi-radiation meter and a GARMIN GPS meter and the result obtained at Raycon, DLA and Neodede Hot Asphalt Mixing Plants for outdoor exposure, shows a total mean value of (0.01492±0.038) (mRh-1), (0.01497±0.037) (mRh-1) and (0.01413±0.014) (mRh-1) respectively. The total mean values obtained in the selected radiological centers were all above the world average BIR level of 0.013 (mR?-1) as recommended by UNSCEAR (2000). These results were used to calculate some hazard indices such as the Equivalent dose (ED) in mSv??1, the absorbed dose rate (ADR) in nGy??1, Annual Effective Dose Equivalent (AEDE) and Excess Life Cancer Risk (ELCR). All the values obtained for each Parameter were above the world permissible limits as given by UNSCEAR (2000). The average activity concentration of 40K, 238U and 232Th in the soil of the three study areas were (603.21±30.94) Bq/Kg, (5.70 ±0.678) Bq/Kg and (6.91 ± 0.405) Bq/Kg. For 40K the average activity concentration was high and above the world recommended limit of 420 Bq/Kg (UNSCEAR 2000). 238U and 232Th were below the world recommended limits which are 33 Bq/Kg and 45 Bq/Kg. respectively. The Activity Concentration results were used to calculate the following radiological parameters: Absorbed gamma dose rate (DR) in (nGy/h), Annual Effective Dose Equivalent AEDE in (?Svy-1), the Radium Equivalent (Raeq), Excess Life Cancer Risk (ELCR) and External Hazard Index. All the calculated radiological Values were above the recommended limit given by (UNSCEAR 2000). Water samples in the study areas was also collected and the average activi

Gamma spectrometer calibration of liquid standard sources of Mix 133Ba, 137Cs and 60Co toward the measurement of 99Mo breakthrough of 99Mo/99mTc generator

The expression radionuclide in nuclear medicine is preferred than radioisotope which widely used in physics. Radionuclides have been used regularly in nuclear medicine. Their radiation provide information about the staging of a person’s specific organs and to specify what is triggering the symptoms, injury or disease to treat diseased organs or cancerous tumours in a patient called theranostic. Technetium-99m radionuclide is the most frequently used radionuclide in nuclear medicine. The quality control of technetium-99m (99m Tc) product from 99Mo/99mTc generator is crucial. One that have been highlighted in this paper is the radionuclide molybdenum-99 (99Mo) breaktrough which can be effectively measured using caliberated gamma spectrometer. The stability test of the gamma spectrometer detector is done using control chart and chi square method from 137Cs radionuclide measurement. The calibration process of liquid standard sources of mix 133Ba, 137Cs and 60Co including energy and efficiency calibration, are performed with the same geometry as Mo99 breakthrough measurement in a lead shield canister with 2.5; 4.5 and 8.5 cm distance from the HPGe detector. The result from the calibration of liquid standard sources of mix 133Ba, 137Cs and 60Co showed the required polynomial equations needed to calculate the 99Mo breakthrough of 99mTc eluted product from the 99Mo/99mTc generator.

Addressing the quantification of meteorological uncertainties in the atmospheric transport simulations of the 133Xe industrial background

The French National Data Center (NDC) uses an automated simulation of the 133Xe worldwide atmospheric background as one of the means to categorize the radionuclide measurements of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) International Monitoring System (IMS). These simulations take into account 133Xe releases from the known or assumed major industrial emitters in the world and global-scale meteorological data. However, a quantification of the simulation uncertainties in this operational set up is yet to be addressed. This work discusses the benefits of meteorological ensemble data as available from National Centers for Environmental Prediction (NCEP) for that purpose. For this study, the daily dispersion of releases from the Institute for Radio Elements (IRE), a medical isotope production facility located in Fleurus (Belgium), was calculated over one year with emissions measured in-site and ensemble meteorological data. The ensemble contains 31 members, which resulted in as many predictions of activity concentration for any given time and place. The resulting distribution statistics (mean, median and spread), and the control run, were confronted to the deterministic run and to measurements at one IMS-like station near Paris (France) and one IMS station in Freiburg (Germany). Overall, the ensemble results have decreased the simulation performance, as expected given the use of meteorological analyses only. However, contrasting patterns were found with a detailed analysis of daily activity concentration over two one-month-and-a-half periods. Noticeably, outlier results were found to carry the best forecast in some significant detections, proving their relevance for the measurement categorization, despite their isolated character. Importantly, the ensemble has allowed the quantification of meteorological uncertainties, which was beneficial in all cases. It either has improved the confidence of IMS data categorization or has pointed to low confidence predictions. A criterion to identify the latter is suggested, based on information provided by the ensemble distributions. In addition, maps of probability of detections and of relative spread are suggested to show additional benefits of ensemble meteorology.

The importance of sampling time in radionuclide measurement of glomerular filtration rate in adults using single blood sample

The importance of sampling time in radionuclide measurement of glomerular filtration rate in adults using single blood sample

Recall of residential history and dietary habits during pregnancy and lactation in the distant past: reliability of questionnaire-based radiation doses for persons exposed in utero and early life.

This study evaluates the reliability of information obtained by standardized questionnaires used in by personal interviews for estimation of radiation thyroid doses of 1065 individuals in the Belarusian cohort of individuals who were exposed in utero and early life following the Chernobyl accident in April 1986. Data from two interviews conducted in 2012-2017 and in 2018-2022 with mothers, who were pregnant or gave birth shortly after the Chernobyl accident, were analysed. The most reliable answers dealt with various attributes related to residential history. In contrast, the reliability of answers regarding consumption rates of milk from privately owned cows or trade network was moderate, while the agreement in responses for consumption of milk products and leafy vegetables was fair. Information from the two interviews was used to calculate thyroid doses received by the cohort members. Specifically, 'model-based' thyroid doses due to 131I were estimated using input data on individual residential history and food consumption reported during the personal interviews and ecological data (131I ground deposition in the corresponding settlements). In addition, for a subset of cohort subjects (n = 205) whose mothers were measured for 131I thyroid activity, 'measurement-based' thyroid doses were calculated by adjusting the model-based dose using a scaling factor that is defined as the ratio of measured 131I thyroid activity to model-based 131I thyroid activity calculated for the date of measurement. A moderate agreement was observed for total (prenatal and postnatal) model-based thyroid doses due to 131I intake, the arithmetic mean ± standard deviation for the Jaccard similarity coefficient ([Formula: see text]) was 0.45 ± 0.34 (median = 0.39), while measurement-based doses showed a much better agreement with a [Formula: see text] of 0.78 ± 0.29 (median = 0.93). For model-based thyroid doses from external irradiation and from ingestion of 134Cs and 137Cs, [Formula: see text] was 0.82 ± 0.23 (median = 0.90) and 0.84 ± 0.24 (median = 0.96), respectively. Measurement-based doses due to ingestion of radiocaesium isotopes resulted in an almost perfect agreement, [Formula: see text] was 0.91 ± 0.19 (median = 1.0). The present findings suggest that long-term memory recall can be reliable, if a person is asked about unique or important life events, such as pregnancy and childbirth occurring around the time of a nuclear reactor accident. However, the substantial difference (more than 10 times) observed for model-bases doses calculated using the two questionnaires represents an important source of human factor uncertainties that needs to be considered in any dose response analyses. Other lessons learned from this study are that (i) individual measurements of radionuclides in the human body are the most valuable source of information for estimating radiation doses, and (ii) whenever a radiation accident occurs, a sample of affected people should be asked to keep a diary, if at all possible.

Status report of the first AMS laboratory in the Czech Republic at the Nuclear Physics Institute, Řež

The first accelerator mass spectrometry (AMS) laboratory in the Czech Republic has been established and put into routine operation in February 2022. Here we briefly describe the facilities available, namely a 300 kV multi-isotope low-energy AMS system (MILEA) capable of determination 10Be, 14C, 26Al, 41Ca, 129I, isotopes of U, especially 236U, Pu and other actinoids, and accessories for 14C measurements, which include a gas interface system, a preparative gas chromatography system for compound-specific radiocarbon dating analysis, and an isotope-ratio mass spectrometer. The first results achieved for separation and measurement of the above radionuclides (except for 41Ca) are also reported, with the main focus on 14C measurements. A specimen breakdown of 729 graphitised samples analysed for 14C so far is presented, as well as a proof of measurement stability of the MILEA system obtained by analysis of radiocarbon standards and analytical blanks. For the other radionuclides, well proven or novel procedures for sample preparation and measurement are presented.

Methodology for the investigation of undeclared atmospheric releases of radionuclides: Application to recent radionuclide detections in Northern Europe from 2019 to 2022

Traces of radionuclides have been frequently detected in the European atmosphere for several years. The measured concentrations are usually very low, ranging from 0.1 to 10 μBq m−3, and do not pose any health or environmental problems.This study aims to diagnose the origin of small undeclared radionuclide releases into the atmosphere. An inverse modelling approach that combines environmental measurements and atmospheric transport modelling is first used to assess the source location of the release. In addition, the type and process of the nuclear facility from which the release could originate are investigated by identifying the isotope production pathways and comparing them with known typical inventories. These two parts of the proposed method are complementary and allow us to extract as much information as possible from a set of radionuclide measurement data.In a previous study, the origins of detections of various radionuclides (60Co, 134Cs, 137Cs, 103Ru, 106Ru, 141Ce, 95Nb, 95Zr) in Finland, Sweden and Estonia in June 2020 have been investigated.In this paper, the previous investigation is extended by analysing two additional events that occurred in northern Europe in July 2019 and May 2022, as well an overview of other unknown releases detected in Finland over the last decade. A more detailed analysis of the 2020 event is also provided by analysing new available environmental measurements.The calculations indicate that the source location of the three events appears to be in the same region, in Russian Federation. The most probable origin of the June 2020 release seems to be a primary ion exchange resin, after 2 to 5 months of decay, of a pressurized water reactor with fuel cladding failure, and dispersion of fissile material in the primary.The July 2019 and May 2022 events are of particularly noteworthy due to the simultaneous presence of 46Sc, which is neither produced nor in the fuel, nor in the primary loop of PWR or RBMK nuclear power plants, and typical corrosion-activated products from power plants (60Co). Two hypotheses are proposed to explain this source term: a mixture of various solid wastes or recently irradiated graphite from a RBMK reactor.The reliability of the methodology is demonstrated, in particular in the section dedicated to atmospheric transport modelling, and the successful association with source term analysis provides a valuable tool for future studies and assessments of both minor and major radionuclide releases.

Development and performance evaluation of a novel [formula omitted]-[formula omitted] coincidence analysis software

Processing of large amounts of data from a γ-γ coincidence system is a practical challenge in trace-level radionuclide measurements. Given the benefits and growing number of multidimensional gamma spectrometers worldwide, this is a major restriction in wide-spread applicability of coincidence techniques. This study demonstrates a novel γ-γ coincidence analysis software developed at Pacific Northwest National Laboratory, USA. The software utilizes advanced search techniques and Python libraries to readily identify coincidence signatures in the large data. Using both synthetic and experimental data, the study uncovers various strategies/libraries employed during software’s development. This work aims to provide a reference document in handling large data routinely encountered in trace-level measurements.

Measurements of Terrestrial Gamma Dose Rate Distributions along Idiroko Road, Ota, Ogun State, Nigeria: Health Implications on Roadside Dwellers

An extensive study concerning the terrestrial gamma dose rates of the surface soils from Canaanland entrance Road, Ota to Eleha Complex along Idiroko Road, Ota has been carried out to cover the road running across both areas. The In-situ measurements of gamma dose rates and radionuclides were carried out using the Gamma detector (Super Spec RS 125). The result shows that the average outdoor gamma dose rate in the study area is 73.57 nGyh−1. The average values of the radionuclides obtained were 32.9 Bq/kg for 238U, 68.4 Bq/kg for 232Th, and 328.7 Bq/kg for 40K. The background dose rate of 113.3 nGy/h was found in station 9 and is twice higher than the recommended permissible limit of 59 nGy/h suggested by UNCSEAR, 2000, and ICRP, 1999, respectively. Results were obtained based on radiological parameters for the outdoor absorbed dose rate (Dout) with a mean value of 73.57 nGyh−1, the indoor absorbed dose rate (Din) with a mean value of 131.84 nGyh−1, the annual effective dose rate (AEDR) with a mean value of 0.74, the radium equivalent (Raeq) with a mean value of 156.0, the internal hazard index (Hin) with a mean value of 0.51, the external hazard index (Hex) with a mean value of 0.42 and the excess lifetime cancer risk (ELCR) with a mean value of 2.57. Similarly, results obtained from estimated radiological parameters show that the station with the highest value for radium equivalent (Raeq), external hazard index (Hex), internal hazard index (Hin), and annual effective dose rate (AEDR) is Station 9 at 237.91 Bq/Kg, 0.64, 0.72 and 1.13 mSvy−1 respectively while the station with the lowest value for radium equivalent (Raeq), external hazard index (Hex), internal hazard index (Hin) and annual effective dose rate (AEDR) is Station 17 at 85.58 Bq/Kg, 0.23, 0.27 and 0.40 mSvy−1 respectively. This study will serve as a guide on assessing the road construction materials on radioactive contents before application to reduce the exposure risks to the populace along the busy roadsides.

Assessment of Radionuclide Concentrations in Catfish and Tilapia fish from Asa-Dam Ilorin, North-central Nigeria

High concentration of naturally occurring radionuclides in food can have adverse effect on human health. Radioactivity measurement of radionuclides in Catfish and Tilapia fish samples from Asa-Dam Ilorin, Nigeria was carried out using gamma ray spectrometer technique. The results of the gamma ray spectrometry were utilized in the estimation of some radiological parameters in the bid to effectively determine the extent of the health implications as regards to radiation from the consumption of fishes in that area. The mean activity concentrations of 40K, 238U and 232Th for Catfish are 37.90±2.83, 8.08±2.71 and 11.73±2.51 Bqkg-1, respectively. Similarly, the mean activity concentrations of 40K, 238U and 232Th for Tilapia are 26.31±3.67, 6.16±2.47 and 8.89±2.19 Bqkg-1, respectively. The mean values of 40K, 232Th and 238U in Catfish were observed to be high when compared to Tilapia. The average absorbed dose rate for both Catfish and Tilapia samples were 12.40 and 9.31 nGyh-1. The mean annual effective doses were 29.65, 276.81, 52.04, 41.10 and 35.00 μSvy-1; 22.41, 209.10, 38.99, 30.93 and 26.43 μSvy-1 for adult, fishermen, 5 years, 10 years and 15 years, respectively for cat and Tilapia fish. The estimated excess lifetime cancer risk for adult, fishermen, 5 years, 10 years and 15 years were 0.10, 0.97, 0.18, 0.14, and 0.12 and 0.09, 0.85, 0.16, 0.13 and 0.11 for both Catfish and Tilapia, respectively. The results of all the radiological parameters estimated showed trends that are generally low, hence, poses no significant radiological health burden.

Risk assessment of naturally occurring radioactivity in soil adjacent to a coal-fired brick kiln

Being aware of the potential health effects brought on by exposure to radionuclides, besides chemical and air pollution, produced by coal-fired brick kilns, first-ever measurements of terrestrial radionuclides were performed in the topsoil sampled from the surrounding of a randomly chosen coal-fired brick kiln operating at the outskirts of megacity Dhaka, Bangladesh. By employing the HPGe gamma-ray spectroscopy, the activity concentrations of 226Ra, 232Th, and 4 K was found to be in the range of (19.2 ± 2.7–54 ± 7.0) Bq/kg, (33 ± 5.3–68 ± 9.5) Bq/kg, and (360 ± 43–540 ± 65) Bq/kg respectively, where almost all the values of 40 K, 232Th; and some of the values of 226Ra exceeded the corresponding world average values. Possible causes of the elevated level of radionuclides include the deposition of bottom ash in lowlands, the accumulation of fly ash in soils, and the fallout of fine particles that absorb the minerals released from the coal burning process. 137Cs was also found in two samples that might indicate contamination of the feed coal. Most of the outdoor absorbed dose rates, some internal absorbed dose rates, annual effective dose, gamma level index and excess lifetime cancer risk surpass the worldwide average. According to these hazard parameters, there are health risks to the brick kiln workers and the populace who consumes food crops produced in the studied agricultural soils. The present quantitative measurements urge the municipal authorities to manage and monitor the discharge of fly ash from the brick kilns and take precautionary actions to reduce unwanted health hazards. It also demands to monitor of the human health of workers and residents near the brick kilns.

Experimental determination of soil sampling uncertainty in the context of environmental radiological monitoring

Uncertainty associated with nuclear counting analyses are attributed to two main components of uncertainty; one is related to sampling, the other to sample preparation and the subsequent nuclear counting. The ISO/IEC 17025 standard of 2017 require accredited laboratories carrying out their own sampling to estimate the uncertainty associated with sampling in the field. This study presents the results of a sampling campaign and analysis by gamma spectrometry to determine the sampling uncertainty related to the measurement of radionuclides in soil.

Development and application of an in-situ shipboard device for the measurement of gamma-ray emitters in seawater

An optimized device based on an HPGe detector and an electro-mechanical cooler combined with a small-sized lead shield was developed for flow-through seawater gamma radionuclide measurement. The system was optimized to operate in mobile or underway mode with suitable integration on available ships. The background spectrum, detection efficiency, and the impact of acquisition time on the minimum detectable activity were obtained at sea. The system MDAs in a 1 h acquisition period for 137Cs (661.7 KeV) and 60Co (1332.5 KeV) in seawater were 0.45 Bq/L and 0.24 Bq/L, and the MDAs in 20 min were 0.73 Bq/L and 0.47Bq/L, respectively. This device could be used as an efficient tool in emergency monitoring in response to a nuclear accident.

Principles and Applications of Accelerator Mass Spectrometry

Accelerator mass spectrometry (AMS) represents an ultrasensitive analytical method for measurement of long-lived radionuclides, namely 14C, 10Be, 26Al, 41Ca, 129I, and 236U. It provides information about isotopic ratios up to 10–16 in samples of mass from several miligrams to tens of micrograms. The first AMS laboratory in the Czech Republic was built in Nuclear Physics Institute, Řež, in collaboration with Archaeological Institute, Prague (both Czech Academy of Sciences) and Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, and equipped with AMS MIELA (Ionplus AG, Switzerland). This review summarizes history, principles, and use of this unique analytical method.

Determination of Plutonium and Other Actinides by Accelerator Mass Spectrometry

Accelerator mass spectrometry (AMS) is a very sensitive method for the determination of ultra-trace concentrations of long-lived radionuclides of actinides, such as uranium, plutonium, neptunium, or americium, mostly in environmental samples. This article focuses mainly on the determination of plutonium isotopes occurring in nature due to human nuclear activity, mainly 239Pu and 240Pu. The determination of the 239/240Pu ratio enables one to identify the origin of plutonium emission in the environment, namely, whether it originates from global fallout or releases from nuclear facilities.
 Actinides determination plays also an important role in environmental studies, where the measurement of individual radionuclides, such as 236U, 237Np, 239Pu, 240Pu and 241Am, can monitor the environmental processes, especially migration, sedimentation or deep ocean currents. The overall sample preparation procedure for AMS includes evaporation and pre-concentration of the sample to reduce its volume or sample decomposition. After that, to eliminate isobaric interferences, it is necessary to separate the actinides from other elements and, in most cases, also from each other. This paper describes procedures of the separation of actinides from various environmental samples, as well as the preparation of the oxide and fluoride target materials which is crucial for the measurement in terms of the isobaric interferences suppression, material quantity and the detection sensitivity.

Development of a single method for direct measurement of multiple radionuclides using ICP-MS/MS

Simultaneous radionuclide measurement in a single procedure using tandem mass spectrometry contributing to rapid, cost-effective nuclear decommissioning and environmental monitoring.

Standardisation of 18F using new portable 4πβ(LS) – λ coincidence detection system at ENEA-INMRI

This project concerned with the development at ENEA-INMRI of new in-situ 4πβ(LS) − λ coincidence detection system for activity measurement of the short half-life radionuclides used in Nuclear Medicine. The hardware of the new portable 4πβ(LS) − λ coincidence detection system was implemented at ENEA-INMRI, in collaboration with Catania University and INFN, by adding a gamma channel on the existing TDCR portable detector available at ENEA-INMRI. A new data analysis software was developed at CAEN, independently from an existing one elaborated at ENEA.INMRI, in order to analyse the data recorded in list-mode by the new detector equipped with the CAEN desktop digitizer DT5720. The activity for short half-life radionuclides used in nuclear medicine can be then computed. Two primary activity measurement TDCR and 4πβ(LS) − λ coincidence methods were then used to determine the activity of 18F at ENEA-INMRI. The TDCR parameter is measured for the 18F standard solution using both CAEN and ENEA-INMRI data analysis software.

Robustness of LabSOCS calculating Ge detector efficiency for the measurement of radionuclides

The LabSOCS software is one of the main simulation codes employed to calculate the full-energy peak efficiency (FEPE) for the measurements of radionuclides by gamma-ray spectrometry. The validity of LabSOCS has not previously been evaluated for a large variety of matrixes, geometry types, and energies. This study aims to analyze in depth the LabSOCS FEPE robustness comparing the LabSOCS and experimental FEPEs by using three coaxial Ge detectors for a wide range of samples, varying the matrix composition, counting geometry (thickness (h) for cylindrical geometry), gamma emission energy (Eγ), and bulk density (ρ). The FEPE averages and variances calculated for numerous matrix types prepared using gamma cocktails were statistically comparable for a wide Eγ range (from 46 keV (210Pb) to 1836 keV (88Y)). To test the accuracy of the LabSOCS FEPEs varying h (6–50 mm), four certified samples containing only natural radionuclides were used. The 234, 228Th, 228, 226Ra, 210Pb and 40K activities were determined for each h, obtaining |zscore| < 2 in general. This also proves the good reproducibility of LabSOCS calculating activity concentrations. The LabSOCS FEPE robustness was also tested for a wide ρ range (1.3–2.8 g cm−3) mixing a sediment sample with Pb(NO3)2 for h = 50 mm. The 210Pb and 234Th contained in each mixture were determined, achieving all |zscore| < 2. Furthermore, the ability of LabSOCS to correct self-attenuation effects was checked to be wider than when other correction models are applied.

A phoswich alpha/beta detector for monitoring in the site of Fukushima Daiichi Nuclear Power Station

Alpha contamination and high concentrations of beta contamination can be found inside the reactor buildings at the Fukushima Daiichi Nuclear Power Station (FDNPS). This study proposes a newly developed phoswich alpha/beta detector that can discriminate alpha and beta particles emitted from the alpha and beta contaminations in the FDNPS site. The phoswich alpha/beta detector is made up of two layers of scintillators that detect alpha and beta particles. The first layer is an octagonal, 50 mm diameter, 40-μm-thick plastic scintillator that measures alpha particles, while the second layer is an octagonal, 50 mm diameter, 50-μm-thick Gd₂Si₂O₇ (GPS) scintillator that measures beta particles. The combination of the two scintillators improves the ability to distinguish between alpha and beta particles. The two layers of scintillators were optically coupled to an 8 × 8 multianode photomultiplier tube (MA-PMT) with 50 mm × 50 mm through a 3-mm-thick light guide (glass plate). An eight-channel 14-bit 500 MS/s digitizer was fed with four output signals. Python programming was used to analyze the collected voltage waveforms. The pulse shape discrimination (PSD) method was used to detect alpha particles in high beta particle and high gamma-ray (comparable to gamma-ray dose rate near the FDNPS reactor building) environments. Due to a 23.3% full width at half maximum (FWHM) energy resolution for alpha particles, the detector can be used to distinguish between nuclear fuel materials such as plutonium and its radon progeny (Po-214). Moreover, the detector could distinguish alpha particles from 137Cs gamma rays with a dose rate background up to 9.0 mSv/h. It is the first to demonstrate that the developed phoswich detector can be used to discriminate and measure alpha and beta particles of the actual contaminated FDNPS samples. As a result, this detector will be effective as an air monitoring device for alpha and beta radionuclide contamination measurement in real time.