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This study investigates the activity concentration of natural radionuclides in a diverse range of food samples in the Koya district markets food baskets, including both domestic and imported products. The samples cover annual crops (e.g. coffee, tea, kidney beans), tree nuts (e.g. almonds, pistachios), and other items (e.g. beef, fish, milk) by using a high-purity germanium (HPGe) detector. This research addresses a notable gap by providing baseline data on radionuclide concentrations and assessing potential health risks. Average activity concentrations for ²²⁶Ra, ²³²Th, and ⁴⁰K were 0.943, 0.367, and 191.8 Bq kg−1, respectively. Radium equivalent activity values ranged from 2.88–58.48 Bq kg−1, all below the safety limit. The average excess lifetime cancer risk (ELCR) was 0.154 mSv a−1, indicating safety for most samples, though coffee and tea showed higher levels. This study provides new data crucial for future research and regulatory monitoring, underscoring the need for further investigation into geological impacts on radionuclide levels. [ABSTRACT FROM AUTHOR]

In this work, radioactivity investigations of soil samples from neutral and agricultural sites in Punjab (India) have been carried out to study the impact of land use patterns. Analyzing soil samples radiological, mineralogical, and physicochemical attributes has employed state-of-the-art techniques. The mean activity concentration of 238U/226Ra, 232Th, 40K, 235U, and 137Cs, measured using a carbon fiber endcap p-type HPGe detector, in neutral land was observed as 58.03, 83.95, 445.18, 2.83, and 1.16 Bq kg−1, respectively. However, in vegetation land, it was found to be 40.07, 64.68, 596.74, 2.26, and 1.90 Bq kg−1, respectively. In the detailed activity analysis, radium equivalent (Raeq) radioactivity is in the safe prescribed limit of 370 Bq kg−1 for all investigated soil samples. However, the dosimetric investigations revealed that the outdoor absorbed gamma dose rate (96.08 nGy h−1) and consequent annual effective dose rate (0.12 mSv y−1) for neutral land and the gamma dose rate (82.46 nGy h−1) and subsequent annual effective dose rate (0.10 mSv y−1) for vegetation land marginally exceeded the global average. The soil's physicochemical parameters (pH, EC, and porosity) from both sites were measured, and their correlations with radionuclides were analyzed. Various heavy metals of health concern, namely, chromium (Cr), arsenic (As), copper (Cu), cobalt (Co), cadmium (Cd), lead (Pb), mercury (Hg), selenium (Se), and zinc (Zn), were also evaluated in soil samples using Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS). Pollution Load Index (PLI) and Ecological Risk Index (RI) revealed that vegetation land was more anthropogenically contaminated than neutral land, with maximum contamination from Hg and As. [ABSTRACT FROM AUTHOR]

In this study, the activity concentration of artificial and natural radionuclides such as 137Cs, 40K, 226Ra, and 232Th was measured in the soil under the roots; leaves; and fruits of six different fruit trees namely mulberry, fig, apricot, olive, black and white grapes in Koya district, Erbil province, Iraq. For this purpose, a high-resolution gamma spectroscopy consisting of a high-purity germanium (HPGe) detector was used. In addition, the associated radiological risks from soil and fruits were assessed by calculating several radiological indices such as radium equivalent (Raeq.s), absorbed dose (Ds), indoor (AEDEsindoor) and outdoor annual effective doses (AEDEsoutdoor), internal and external hazard indices, gamma index and the excess lifetime cancer risk (ELRCs). The results show that consuming these fruits is radiologically safe because they can cause an annual effective dose of about 61.72 μSv y−1 and excess lifetime cancer risk of 0.06 × 10−3 Sv y−1. On the other hand, transfer factors of radionuclides from soil to leaves; and from soil to fruits were studied. The transfer factor analysis revealed that among the studied fruits and radionuclides, apricot and mulberry exhibited the highest transfer factors for 40K, with values of 1.85 and 1.87, respectively. [ABSTRACT FROM AUTHOR]

Modeling the response of gamma detectors has long been a challenge within the nuclear community. Significant research has been conducted to digitally replicate instruments that can cost over USD 100,000 and are difficult to operate outside of a laboratory setting. The large cost and availability prevent some from making use of such equipment. Subsequently, there have been multiple attempts to create cost-effective codes that replicate the response of sodium-iodide and high-purity germanium detectors for data derivation related to gamma-ray interaction with matter. While robust programs do exist, they are often subject to export controls and/or they are not intuitive to use. Through the use of hybrid Monte Carlo methods, MATLAB can be used to produce a fast first-order response of various gamma-ray detectors. The combination of a graphical user interface with a numerical-based script allows for open-source and intuitive code. When benchmarked with experimental data from Co-60, Cs-137, and Na-22, the code can numerically calculate a response comparable to experimental and industry-standard response codes. Evidence supports both savings in computational requirements and the inclusion of an intuitive user experience that does not heavily compromise data when compared to other standard codes, such as MCNP and GADRAS, or experimental results. When the application is installed on a Dell Intel i7 computer with 16 cores, the average time to simulate the benchmarked isotopes is 0.26 s. Installation on an HP Intel i7 four-core machine runs the same isotopes in 1.63 s. The results indicate that simple gamma detectors can be modeled in an open-source format. The anticipation for the MATLAB application is to be a tool that can be easily accessible and provide datasets for use in an academic setting requiring gamma-ray detectors. Ultimately, this article provides evidence that hybrid Monte Carlo codes in an open-source format can benefit the nuclear community in both computational time and up-front cost for access. [ABSTRACT FROM AUTHOR]

The objective of this study is to assess natural activity in soil to estimate potential radiological risks for the population. Given that soil is inherently radioactive and can reach hazardous levels, it is crucial to determine the activities of radionuclides such as Potassium-40 and Uranium-238 descendants at different depths and geographical positions. For this work, gamma spectrometry method was employed to analyze soil samples collected at three different positions in the Missour region. Each position was sampled at five different depths, spaced 5 cm apart, resulting in a total of 15 samples. The activity of Potassium-40 and Uranium238 descendants in the soil was accurately assessed using Lvis software, enabling the estimation of radiological doses. [ABSTRACT FROM AUTHOR]

Natural radionuclide activity concentrations were measured in ceramic, gypsum, and brick samples from manufacturers, dealers, and construction sites in and around Addis Ababa, Ethiopia, using an HPGe detector. The study's main aim is to assess the activity concentration of building materials and their health impacts. Average activity concentrations (Bq kg−1) for 226Ra in ceramic, gypsum, and brick samples were obtained as 81 ± 1, 1.34 ± 0.17, and 39 ± 1, respectively. In ceramic, gypsum, and brick, concentrations of 232Th were obtained as 166 ± 4, 0.68 ± 0.18, and 103 ± 3, respectively, while concentrations of 40K were found to be 755 ± 16,15 ± 1, and 921 ± 24, respectively. Some of the materials that were tested, especially the ceramic samples, had slightly higher concentrations of radionuclides in comparison to other analysed samples. In all samples except ceramic, Raeq was < 370 Bq kg−1, which is the recommended limiting dose for bulk medium. Furthermore, the corresponding radiological parameters, such as absorbed dose, annual effective dose equivalent, excess lifetime cancer risk (ELCR), internal (Hin) and external (Hex) hazard indexes, gamma index (Iγ), and alpha index (Iα) were determined. The ELCR average values in this study are slightly higher than the global average, and the indoor and outdoor absorbed dose rates are greater than the limiting criteria of 84 and 59 n Gy h−1, respectively. Therefore, it is important to assess the potential radiation risk of ceramic samples, which should be used in a controlled manner to reduce gamma exposure to residents. Finally, the computed data could be used as a baseline to assess any future radiation exposure from construction materials. [ABSTRACT FROM AUTHOR]

In this study, the current status of natural and artificial radioactivity levels in soil samples from the Büyükçekmece and Silivri districts of Istanbul, as well as the Marmara Ereğlisi district in Tekirdağ, has been determined in anticipation of a potential nuclear leakage (e.g. the Zaporizhzhia Nuclear Power Plant). Twenty soil samples were collected from the study area, and the radioactivity concentrations of 226Ra, 232Th, 40K and 137Cs were measured using an HPGe detector. The average concentrations of 226Ra, 232Th, 40K and 137Cs were found to be 26 ± 2, 30 ± 2, 540 ± 29, 0.55 ± 0.07 Bq kg−1, respectively. [ABSTRACT FROM AUTHOR]

The integration of the ORION digital signal processing-based MCA system coupled with a 3″ × 3″ NaI(Tl) detector assembly with a GM detector for counting beta (β) has eliminated the need for a standalone β-γ method in which U3O8 is determined by gross β and gross γ counting. Uraniferous and mixed U-Th samples were taken up for study and compared with the results obtained from Canberra p-type coaxial high resolution gamma ray spectrometry detector. In uraniferous samples, U3O8 values obtained are within ±10%, whereas in the case of mixed U-Th samples, U3O8 values are within ±15%. Regression graphs drawn between the outcomes from the two analytical systems indicate R2 > 0.95 for Ra(eU3O8) and ThO2. In uraniferous samples, the R2 value for U3O8 was found to be > 0.99, but in mixed U-Th samples, it is 0.92. The closeness of agreement between the results obtained from two methods at various concentrations over the analytical range shows that the integrated system is suitable for the quantitative determination of eU3O8, U3O8, Ra(eU3O8), ThO2 and K in geological rock samples. [ABSTRACT FROM AUTHOR]

The asteroid impacts can be devastating for the life on the Earth. Thus, mitigation of this unwanted event is of crucial importance, and nuclear devices are state-of-the-art choice. The presented paper focuses on nuclear data validation of silicon and oxygen. Nuclear data validation is an essential task because nuclear data are the deciding factor for energy deposition profiles, which serve as input for subsequent hydrodynamic simulation, thus directly affecting the description of asteroid deflection. The silicon and oxygen in the form of silicate materials are abundant in asteroids. The set of neutron and gamma transport experiments using a primary neutron standard 252Cf neutron source was performed. The fast neutron spectrum in the energy range of 2–10 MeV was measured using a stilbene detector. The best agreement for fast neutron leakage spectra was reached using INDEN evaluation for 28Si and ENDF/B-VIII.0 16O evaluation. Activation foils sensitive in different energy ranges were utilized. The results depend on the examined reaction and distance from the source. Finally, the prompt gamma rays from capture and inelastic scattering were measured by an HPGe detector. With the exception of 28Si(n,n′) 1779 keV peak, other prompt gamma production peaks show significant discrepancies. The calculations for comparisons of different transport libraries were performed using Monte Carlo MCNP6.2 code. The results show the necessity of further improvement of evaluations for oxygen and silicon. • Energy deposition profile highly depends on used transport library. • Effect of different transport libraries on calculations. • Measurement of leakage neutron spectra from sand cylinder • Measurement of reaction rates of activated materials. • Measurement of prompt gammas. [ABSTRACT FROM AUTHOR]

The mass fractions of Fe and B as well as the isotopic compositions of B were non-destructively and simultaneously quantified in synthetically prepared ferroboron (Fe–B) alloys by external particle induced gamma ray emission (PIGE) method using a proton beam of 3.5 MeV. Powder samples were wrapped in a thin Mylar foil and kept in front of the target flange in the atmosphere for irradiation using an external PIGE set up. Characteristic prompt gamma rays of 56Fe(p,p′γ)56Fe (847 keV), 10B(p,αγ)10B (429 keV), 10B(p,p′γ)10B (718 keV) and 11B(p,p′γ)11B (2125 keV) nuclear reactions were measured together with external beam current normalizers of 136 keV of 181Ta(p,p′γ)181Ta (beam extraction/window material) and 2313 keV of 14N(p,p′γ)14N (atmospheric nitrogen) using an HPGe detector system. Boron mass fractions determined using 429 keV gives better precision than those determined using 718 and 2125 keV with 136 keV of Ta as a current normalizer after irradiating the samples only for 10–15 minutes owing to a high proton-induced thick target gamma ray yield of 429 keV at 3.5 MeV. Isotopic compositions of B determined with simple peak area ratios of 429 and 718 keV of 10B and 2125 keV of 11B are 0.248 (4) and 0.246 (2), respectively, which correspond to 19.8 atom% of 10B, i.e. natural sample. Mass fractions of Fe, which is the major constituent of Fe–B alloy, were also determined simultaneously with B. The advantage of this external PIGE method is the analysis of direct powder samples with minimal sample preparation providing high sample throughput and faster results with adequate accuracy and precision. [ABSTRACT FROM AUTHOR]

In this work we investigated new different glass compositions 20PbO–20BaO–(60 − x)B2O3–xZnO (x = 0, 5, 10, 15 and 20 mol%) to study the radiation shielding capability of these glass composites. The shielding ability was measured experimentally using narrow beam method (which including HPGe detector, point sources and lead collimators). The accuracy was verified by XCOM software, the linear attenuation coefficient (LAC) of the produced glasses was ascertained using both methods. We noticed that the B40Z20 glass composite (contain 20 mol%) has the highest LAC at the four examined energies (0.060, 0.662, 1.173 and 1.333 MeV) since the LAC enhances as the ZnO content increases from 0 to 20 mol%. The based shielding parameters such as HVL and RSE or called radiation shielding efficiency were determined experimentally. The HVL reduces as the glasses' density (or, more accurately, the amount of ZnO) increases. At 0.06 MeV, the HVL have the following values: 0.041, 0.039, 0.038, 0.036 and 0.035 cm for the glasses with density of 3.582, 3.739, 3.897, 4.055 and 4.212 g/cm3 respectively. [ABSTRACT FROM AUTHOR]

Determination of the environmental radioactivity concentration value is very important as it directly effects human health. Natural and artificial radionuclide concentration levels have been determined by looking 226Ra, 232Th, 40K, and 137Cs radionuclides. In this study, natural and artificial continental radionuclide concentrations were measured in the Bandirma district of Balikesir. 226Ra, 232Th, 40K, and 137Cs radioactivity concentrations were detected with the aid of a high-purity germanium (HpGe) detector. Soil samples used in the study were selected from 30 different locations sampling points located in Bandirma. The radiological hazard indices such as absorbed gamma dose rate (D), annual gonadal dose equivalent (AGDE), exposure dose (ER), total annual effective dose (AED), excess lifetime cancer risk (ELCR), internal hazard index (Hin), external hazard index (Hex) and gamma representative level (GRL) were determined. The mean values of 226Ra, 232Th, 40K, and 137Cs concentrations in this study were 15.81 ± 1.35 Bq kg−1, 28.86 ± 1.07 Bq kg−1, 276.86 ± 11.69 Bq kg−1, and 1.98 ± 0.31 Bq kg−1 respectively. The calculated radiological hazard parameters were compared with the world averages. The obtained radioactivity concentration values were measured to be below the world average. [ABSTRACT FROM AUTHOR]

The influence of uncertainty on the method adopted for the determination of radioactive radium concentration in water was analyzed due to the assessment of the radiation hazards of balneotherapy. For the calculation, we considered the influence of the bath in radioactive water containing only 226Ra. 226Ra concentration was determined with two γ-spectrometers armed with HPGe detectors with different relative efficiencies. Both spectrometers were energy-efficiency calibrated with a calibration source and based on numerical simulations. Different methods for qualitative γ-spectrum analysis were adopted. The emanation method and the liquid scintillation method were also used. The uncertainty of humans hazard assessment linearly depends on the adopted radiometric method precision. For effective dose calculation, two models were adopted: the model of external exposure proposed by ICRP Publication 144 and the Reference Men model proposed by ICRP Publication 23, respectively. [ABSTRACT FROM AUTHOR]

A coaxial type HPGe detector, and two lanthanide scintillation type detectors have been modeled and characterized by means of Monte Carlo method implemented using the MCNP code. The isotope of interest is 88Rb which decays with energies up to 5 MeV, and can in theory aid in extending the efficiency calibration of the installations of interest in higher gamma rays energies. An 152Eu point source was used for the experimental validation of the MCNP models and excellent agreement was observed between the experimental data and the simulated data of both 152Eu and 88Rb point sources. After the experimental validation of the model, the efficiency calibration was extended for three different source-to-detector distances and the results are presented in this work. [ABSTRACT FROM AUTHOR]

The presence of underlying uranium deposits may contaminate the upper soil of a region. We have carried out a detailed investigation of radionuclides (Ra, Th, and K) present in the soil around the reported uranium deposit site in the Sikar district of Rajasthan, India. Measurements are carried out using the state-of-the-art gamma-ray spectroscopy (HPGe detector) technique. The specific activity of 226Ra, 232Th, and 40K are found in the range of 9.5 ± 0.5–50.6 ± 1.0 Bq kg−1, 11.0 ± 0.4–83.2 ± 1.5 Bq kg−1, and 177 ± 13–753 ± 47 Bq kg−1 with the mean values of 17.8 ± 7.5 Bq kg−1, 22.6 ± 13.4 Bq kg−1, and 393 ± 76 Bq kg−1 respectively. The average value of Ra Eq. activity is 80.4 Bq kg−1, below the recommended limit of 370 Bq kg−1. For radiological implications in the study area, the indoor and outdoor absorbed dose rates and age-dependent annual effective dose are estimated, which are also found below their prescribed safe limit values. The mean value of other hazard indices (Hin and Hex) and level indices (Iα and Iγ) are less than unity. Our study shows that the underlying uranium deposits do not contaminate the soil of the studied area and the soil is safe to use for various purposes. [ABSTRACT FROM AUTHOR]

High purity germanium (HPGe) detectors are deployed globally for gamma-radiation spectroscopy due to their superior energy resolution. In this work, the essential characteristics of n and p-type HPGe detectors, such as energy resolution, efficiency, minimum detectable activity (MDA), and peak shape were studied for the purpose of characterization and performance optimization. The results are obtained for various source-detector configurations in a wide energy range of 40–1408 keV using gamma sources, such as 109Cd, 57Co, 137Cs, 54Mn, 65Zn, 60Co, and 152Eu. Scanning (distance, lateral, and radial) of the detectors was performed using different gamma sources to understand the orientation of the crystal with its active volume and counting efficiency and to characterize the geometry in detail. The ambient background around the n-type HPGe was reduced using Pb-shielding. As a result, an 85.85% suppression was observed in the mean integral window of 40–2700 keV. The characterization and performance tests of the detectors convincingly suggest that both the detectors can be deployed for environmental radioactivity explorations. [ABSTRACT FROM AUTHOR]

The concentration of natural radionuclides (226Ra, 232Th, 40K) in the fifty soil samples around the Khetri copper belt is measured using an HPGe detector. The values of 226Ra, 232Th, and 40K are found to be lying in the range of 5.2 ± 0.3 to 27.5 ± 0.6 Bq kg−1, 12.9 ± 0.4 to 38.8 ± 1.3 Bq kg−1, and 113.3 ± 27.8 to 308.5 ± 31.2 Bq kg−1 respectively. The radium equivalent activity ranged from 38.63 to 93.35 Bq kg−1 with a mean value of 56.21 Bq kg−1. The values of absorbed dose rate, annual effective dose, and annual gonadal dose rate are also estimated, which comes out to be less than their corresponding world average values. Hazard indices (internal and external) and level indices (alpha and gamma) are also observed to be less than unity. The soil of the study area can be considered safe for people living there because of its low radiological risk. [ABSTRACT FROM AUTHOR]

This study represents the findings of the measurement of natural radioactivity in soil and water samples collected from the upper Himalayas region along the Manali–Leh Highway. The activity concentration values of terrestrial radionuclides in soil samples are measured using an n-type HPGe detector. The radiological hazards are also estimated through the evaluation of radium equivalent activity (Req), external and internal hazard index (Hex, Hin), alpha index (Iα), gamma index (Iγ), air absorbed dose, and indoor and outdoor effective dose. The level of Uranium in surface and ground water samples collected from the region is determined using the LED Fluorimetry technique. Annual effective dose, radiological and chemical toxicity risk, and hazards quotient due to the presence of uranium in water samples are also calculated. The values of these parameters are compared with permissible limits. [ABSTRACT FROM AUTHOR]

This paper describes a procedure for the estimation of 241Am and 239Pu activity present in the human tissue by measuring the depth of contaminant using a portable Planar High Purity Germanium detector (HPGe). The ratios of photopeak counts of X-rays or gammas obtained with the detector coupled to collimator are calculated for the estimation of depth of the contaminant and the optimum one is determined. Since Minimum Detectable Activities (MDA) for the detector coupled to a collimator are higher than that of bare detector, activity must be estimated using bare detector, after locating the contaminant. Two methods are described for the estimation of plutonium coexisting with 241Am: (i) Abundance and isotopic correction for 239Pu (ii) and 239Pu:241Am ratio. The procedure to estimate 239Pu when plutonium isotopes alone are present is also established. An optimum monitoring period to detect the minimum value of intake for both radionuclides corresponding to chelation therapy and excision is also derived. [ABSTRACT FROM AUTHOR]

Radionuclide contamination is a serious health issue caused by nuclear experiments and plant accidents, as seen for the Chernobyl and Fukushima nuclear plants. Italy has been especially interested in northwestern alpine regions, as have several other nations. The aim of this work was to indagate 134Cs and 137Cs contamination in wild boars, which were considered bioindicators sampled in the Chisone/Germanasca Valley and the Pellice Valley districts (Piedmont, Italy) in two hunting seasons (2014 and 2016). In the 2014 season, only the livers of the animals (n = 48) were sampled, whereas in 2016, five different anatomical sampling sites were sampled for each animal (n = 16). The analyses were conducted in an accredited laboratory (Agenzia Regionale per la Protezione dell'Ambiente–ARPA) by the aid of an HPGe detector (Ortec) with a relative efficiency of 50%. In general, the contamination levels registered in 2014 were under the detection limit for 134Cs and low for 137Cs (Chisone/Germanasca valley: min: 0.0, max: 23.9 median 11.0 Bq/kg vs Pellice valley: min 0, max: 31.7, median: 9.6 Bq/kg) and no health concern can be supposed. In the first-year samples, the liver showed a negative correlation between age and contamination level. In the second year of sampling, low levels were confirmed (min: 3.1 Bq/kg, max: 113.3; median 17.7 Bq/kg). Multiple sampling from the same animal showed that the diaphragm (median = 27.7 Bq/kg) kidney (27.4) and tongue (27.6) were more contaminated than the liver (17.7) and spleen (15.3). Moreover, a linear mixed model revealed a negative organ-by-age interaction, meaning that interorgan differences in contamination level were greater in younger (5–11 months) than in older (18–36 months) animals. Different feeding habits can be the explanation. Our paper shows that muscle sites (diaphragm and tongue) can be useful for radionuclide pollution surveillance in wild boar populations and that younger animals show more interorgan variability in contamination levels than older animals. More investigations are needed to confirm this correlation and to fulfill the request for more data to achieve better risk assessment. [ABSTRACT FROM AUTHOR]

This work determined the gamma and X-rays emission intensities per 100 decays of 153Sm, in the energy range of 40–172 keV, with a coaxial HPGe detector. The main values of gamma-ray emission intensities were 103.18 keV (28.70(18)) and 69.67 keV (4.90(05)), and X-rays 41.54 keV (29.30(31)). The inclusion of more points in the efficiency curve improved the results, despite the use of only one spectrometer for the entire proposed energy range. The use of anticoincidence standardization and HPGe photon spectrometry plus peak deconvolution methods in low-energy regions allowed for more reliable decay data for 153Sm. [ABSTRACT FROM AUTHOR]

The potential of prompt gamma analysis based on inelastic scattering of 2.5 MeV neutrons for a rapid characterization of NdFeB permanent magnets is investigated by means of numerical simulations using an HPGe detector and a CZT detector-array. The results show that rapid assay of a 42 g magnet can be achieved in some minutes when the neutron flux at sample position is about 1.6 × 109 cm−2 s−1 and the detector count rate limited to 500 kcps. Such a high neutron flux could be delivered by a compact 5 MeV proton accelerator with a thick beryllium target for neutron production through the 9Be(p,xn)9Be. [ABSTRACT FROM AUTHOR]

The nu-Ball2 experimental campaign at the ALTO facility in France involved the use of a hybrid gamma-ray spectrometer to perform measurements related to nuclear fission and neutron-rich nuclei. The spectrometer consisted of different types of detectors, including high-resolution clover Germanium detectors and Bismuth Germinate Oxide (BGO) anti-Compton shields. The campaign aimed to better understand the fission process and study the nuclei produced as a result. The setup allowed for flexibility in coupling different detectors and utilized a fully digital data acquisition system. The campaign resulted in a large amount of data and involved international collaboration. [Extracted from the article]

The distribution of natural series radionuclides 226Ra, 232Th and non-series 40K in the heavy mineral-rich beach sands of highly touristic areas of Cox's Bazar sea beach has been studied. The study is made to evaluate the gamma radiation exposure to individuals with an aim to establish reference data for the presence of naturally occurring radionuclides. The present study reports the probable first attempt of detail and systematic work in the study areas for estimation of activity concentration in the recent beach sand samples. Radiometric analysis was performed using gamma ray spectroscopy system based on HPGe detector. The mean activity levels of 226Ra, 232Th and 40K in Laboni beach sands were ranged from 255.69±64.57, 336.83±93.96 and 1785.91±89.60 Bq kg-1, respectively. While in Kolatoli beach sands, the respective values were 166.42±35.99, 157.35±35.90 and 1894.42±74.07Bq kg-1, respectively. The mean values of 226Ra and 232Th concentrations in the investigated beach sands were estimated to be very much higher than the corresponding world average values and comparable to those found in high background radiation areas in the world. The heavy minerals seem to control the activity concentrations of 226Ra and 232Th in sand samples, showing some variances based on uranium and thorium bearing minerals. Various radiation health hazard indicators were found to be extremely higher when compared to the recommended values. Hence, heavy mineral-rich sands may pose a significant radiological health risk to the people. The descriptive statistics indicating the radionuclides of 226Ra, 232Th and 40K are uniformly and symmetrically distributed in the Cox's bazar beach sand. Multivariate statistical analysis showing the radioactivity and estimated radiological parameters are strongly positively correlated with 226Ra and 232Th, while weakly correlated with 40K, signifying that radiological risk is mainly associated and controlled by the radioactivity levels of uranium and thorium series radionuclides. [ABSTRACT FROM AUTHOR]

(1) Background: Generally, in nuclear medicine and nuclear power plants, energy spectrum measurements and radioactive nuclide identification are required for evaluation of strong radiation fields to ensure nuclear safety and security; thereby, damage is prevented to nuclear facilities caused by natural disasters or the criminal smuggling of nuclear materials. High count rates can lead to signal accumulation, negatively affecting the performance of gamma spectrometers, and in severe cases, even damaging the detectors. Higher pulse throughput with better energy resolution is the ultimate goal of a gamma-ray spectrometer. Traditionally, pileup pulses, which cause dead time and affect throughput, are rejected to maintain good energy resolution. (2) Method: In this paper, an ultra-throughput boost (UTB) off-line processing method was used to improve the throughput and reduce the pileup effect of the spectrometer. Firstly, by fitting the impulse signal of the detector, the response matrix was built by the functional model of a dual exponential tail convolved with the Gaussian kernel; then, a quadratic programming method based on a non-negative least squares (NNLS) algorithm was adopted to solve the constrained optimization problem for the inversion. (3) Results: Both the simulated and experimental results of the UTB method show that most of the impulses in the pulse sequence from the scintillator detector were restored to δ-like pulses, and the throughput of the UTB method for the NaI(Tl) spectrometer reached 207 kcps with a resolution of 7.71% @661.7 keV. A reduction was also seen in the high energy pileup phenomenon. (4) Conclusions: We conclude that the UTB method can restore individual and piled-up pulses to δ-like sequences, effectively boosting pulse throughput and suppressing high-energy tailing and sum peaks caused by the pileup effect at the cost of a slight loss in energy resolution. [ABSTRACT FROM AUTHOR]

Human beings are constantly exposed to the radiations coming from the environment. This work assesses the radiological hazards of natural radioactivity in soil samples taken at four locations around the phosphate area in south Tunisia. Concentrations of primordial radionuclides were measured by gamma spectrometer using an HPGe detector. The overall mean values of 40K, 226Ra and 232Th concentrations were 264, 27 and 13 Bq kg−1, respectively. From the radioactivity measurements, radiation hazard indices specified by the United Nation Scientific Committee on the Effect of Atomic Radiation such as radium equivalent activity (Raeq), absorbed dose rates (⁠|$ {\dot{\text D}} $|⁠) and annual effective dose (AED) to the population for outdoor environment were determined. The mean values for the abovementioned parameters were 64 Bq kg−1, 33 nGy h−1 and 40 μSv y−1, respectively. [ABSTRACT FROM AUTHOR]

High Resolution Gamma-ray Spectroscopy (HRGS) and Total Absorption Gamma-ray Spectroscopy (TAGS) techniques of beta decay study and facilities for such techniques at VECC, Kolkata have been described. The preliminary results of the HRGS experiment performed at VECC to study the beta decay of 126Sb, an important nucleus for the reactor decay heat estimation, are presented. The observation of a 928-keV gamma ray confirmed the 2703.6 keV state in 126Te. The half-lives of both the beta-decaying states in 126Sb could be uniquely measured in this work. The results are useful for future TAGS measurements of the 126Sb beta decay. [ABSTRACT FROM AUTHOR]

In this work, a total of 20 water samples were collected from various locations inside the city of Baghdad. Each sample consists of a volume of 1 litre of water which had been obtained from multiple geographical locations. There were twelve water samples representing pure tap water sourced from various locations additionally, eight samples of mineral water were obtained from several marketplaces in Baghdad. A total of six radionuclides were detected in the water samples using the HPGe detector. These radionuclides were identified as Bi 214, Ra 226, TI 208, Bi 212, Pb 212, and K 40. Among these, Bi 214 and Ra 226 are part of the U-238 series, while TI 208, Bi 212, and Pb 212 belong to the Th 232 series. Additionally, K 40 is a naturally occurring radionuclide. The observed minimum value for the average specific activity of radionuclides in pure tap water samples was Al-Yarmouk Pure tap water. However, the sample Hay Al-qahira pure tap water exhibited the highest recorded specific activity values of radionuclides in pure tap water. The observed minimum value for the average specific activity of radionuclides in mineral water samples was Bardaa mineral water. However, the sample (W15) exhibited the highest recorded values for the specific activity of radionuclides in mineral water. The measured external dosage of natural radioactivity in water samples from Baghdad was found to be relatively low, at 0.366 mSv.y-1. This value falls below the recommended limit the United Nations Scientific Committee set on the Effects of Atomic Radiation (UNSCEAR), 1 mSv.y-1. [ABSTRACT FROM AUTHOR]

Miners, factory workers, traders, end-users, and foodstuff consumers all run the risk of encountering health hazards derived from the presence of elevated levels of radiation in fertilizers, as these groups often come into direct or indirect contact with fertilizers as well as raw materials throughout various linked processes such as mineral extractions, fertilizer production, agricultural practices. A total of 30 samples of various kinds of fertilizer produced in different factories in Dhaka megacity were analyzed to quantify the concentrations of primordial radionuclides using HPGe detector. Among the analyzed samples, average (range) concentration of 40K was found to be 9920 ± 1091 (8700 ± 957–11,500 ± 1265), 9100 ± 1001 (8600 ± 946–9600 ± 1056), 2565 ± 282 (2540 ± 279–2590 ± 285), and 3560 ± 392 (2620 ± 288–4500 ± 495) Bq/kg in the samples of Muriate of Potash Fertilizer, Sulphate of Potash Fertilizer, Humic Acid Fertilizer, and NPKS Fertilizer, respectively. Elevated concentration of 226Ra was found in Triple Super Phosphate Fertilizer with a mean (range) of 335 ± 37 (290 ± 32–380 ± 42) Bq/kg. The higher activity of 40K can be linked to the greater levels of elemental potassium in phosphate fertilizer. Elevated concentrations of radionuclides may also result from variations in chemical processes as well as the local geology of the mining areas where the raw materials were extracted for fertilizer production. Numerous fertilizer brands surpass prescribed limits for various hazardous parameters, presenting significant health risks to factory workers, farmers, and consumers of agricultural products. This study provides baseline information on the radioactivity of fertilizers, which could be used to develop mitigation methods, establish national fertilizer usage limits, justify regulatory frameworks, and raise public awareness of fertilizer overuse. The findings of the study could potentially help to explore the impact of fertilizer on the food chain. [ABSTRACT FROM AUTHOR]

Uranium concentration and uranium isotopic content are two important and critical parameters for any nuclear fuel fabrication facilities. In the present study emphasis has been given on the usage of high resolution gamma ray spectrometric (HR-GRS) technique with HPGe detector for the determination of uranium and 235U content in uranium process stream samples. The work has been carried out with an aim to give quick analytical feedback to production facility and also to minimize the generation of analytical waste. These are important requirements for any industrial lab with high analytical load attached to production facility. In this paper a simple and a non-destructive testing (NDT) method has been described for quantification of uranium and 235U content in samples received from UO2 fuel production facilities using HR-GRS technique with high purity germanium (HPGe) detector. A 185.7 keV line of 235U has been used for quantification of uranium in process solutions containing 1 g/L to 600 g/L of uranium covering both aqueous and organic process stream solutions. The results have been compared with that of Davies and Gray method. The limitations associated with gamma ray emitted from daughter products of 238U and self-induced or self-excited X-ray fluorescence lines of uranium have also been studied. Multi Group Analysis of Uranium (MGAU) software code has been used for measurement of 235U content in variety of samples. The results obtained are compared with that of results by thermal ionization mass spectrometer (TIMS). [ABSTRACT FROM AUTHOR]

This paper focuses on the research and development of high-purity germanium (HPGe) crystals for detector fabrication, specifically targeting applications in rare-event physics searches. The primary objective was to produce large-scale germanium crystals weighing >1 kg with a controlled diameter of ∼10 cm and an impurity range of approximately 10 10 /cm   3 . Ensuring structural integrity and excellent crystalline quality requires a thorough assessment of dislocation density, a critical aspect of the crystal development process. Dislocation density measurements play a crucial role in maximizing the sensitivity of HPGe detectors, and our findings confirmed that the dislocation density fell within acceptable ranges for detector fabrication. Additionally, this paper examines the segregation coefficient of various contaminants during the crystal development process. Comprehensive analysis of impurity segregation is essential for reducing contaminant quantities in the crystal lattice and customizing purification processes. This, in turn, minimizes undesired background noise, enhancing signal-to-noise ratios for rare-event physics searches and overall detector performance. The investigation included the segregation coefficients of three major acceptors and one donor in crystals grown at the University of South Dakota, providing valuable insights for optimizing crystal purity and detector efficiency. [ABSTRACT FROM AUTHOR]

The cross sections for the reactions 132Xe(n,d*)131I and 134Xe(n,d*)133I were measured at energies around 14 MeV. The neutron fluence standard corresponds to the cross-section of the monitor reaction 93Nb(n,2n)92mNb. The facilities from the China Academy of Engineering Physics (CAEP) were used for this experimental study. High purity, high-pressure, and highly enriched 132,134Xe isotope gases were used as the target sample. The T(d,n)4He reaction was used as a neutron source to generate neutrons with an energy of 14 MeV. The activities of the resulting residual product were measured using an HPGe detector. The corrected experimental parameters include the geometric properties and solid angle of the sample, as well as the effects of coincidence summation and self-attenuation of the gamma ray. The covariance analysis technique is employed to derive the uncertainty and correlation matrix of the cross section. The cross sections of the reactions 132Xe(n,d*)131I and 134Xe(n,d*)133I have experimentally been determined and reported for the first time. The TALYS-1.96 program was used to derive the theoretical excitation function curves for the nuclear reactions 132Xe(n,d*)131I and 134Xe(n,d*)133I. All results are compared, including experimental measurement, theoretical calculation, and evaluation. The reaction cross section obtained for the first time plays an important role in enhancing the database and evaluating the excitation function. [ABSTRACT FROM AUTHOR]

An optical phased array (OPA) with 2-D circular sparse array aperture has been proposed and demonstrated in the silicon integrated photonic platform. The sparse distribution of the antenna array can realize no grating lobes in 2-D full field of view (FOV). To achieve fast and accurate phase calibration for OPA, an improved rotating element electric field vector algorithm based on golden section search method (GSS-REV) has also been proposed and verified. The 32-element antenna sparse distribution of the proposed OPA is designed and fabricated. A far-field beam steering measurement across 20° × 20° range features the side lobe suppression ratio (SLSR) of larger than 4.81 dB and a full width at half-maximum (FWHM) of approximately 0.63° × 0.59°. The resolvable points are derived to be ∼1076. The OPA chip has also been demonstrated on range measurement with frequency-modulated continuous-wave (FMCW) system. [ABSTRACT FROM AUTHOR]

The aim of this study is to create a radiological map of Kırşehir province in Turkey by analyzing the radioactivity levels of soil samples and environmental radiation measurements. 226Ra, 232Th, 40K and 137Cs radionuclides were analysed in soil samples collected from 47 locations using gamma spectrometry with an HPGe detector. According to the results obtained, gamma radioactivity concentration ranges and mean values for 226Ra, 232Th, 40K and 137Cs were determined as 133 ± 15–1515 ± 128 Bq/kg (599.40 Bq/kg), 0.3 ± 0.09–21.1 ± 1.7 Bq/kg (4.61 Bq/kg), 8.7 ± 0.9–128.5 ± 8.5 Bq/kg (29.66 Bq/kg) and 11.6 ± 8.6–273.8 ± 19.9 Bq/kg (48.80 Bq/kg) respectively. Average radioactivity levels for 40K and 232Th are above the world average. The mean radium equivalent activity (Raeq), gamma dose rate (D), annual effective dose equivalent (AEDE), external hazard index (Hex), and the excess lifetime cancer risk (ELCR) were calculated as 145.45 Bq/kg, 122.13 nGy/h, 0.15 mSv/h, 0.39 and 0.29 × 10−3 respectively. [ABSTRACT FROM AUTHOR]

In this paper, the details of the development and performance characterisation of a compact, low-power gamma spectrometer for environmental gamma radiation monitoring networks are presented. To reduce the power consumption and the size of the spectrometer, a gamma detector comprising a silicon photomultiplier coupled to a Gd3Ga3Al2O12:Ce,B (GGAG:Ce,B) scintillator has been used for gamma spectrometry. Initially, a Monte Carlo simulation study was carried out to verify the suitability of the 5 mm × 5 mm × 5 mm GGAG:Ce,B crystal for spectrometry of gamma sources in the energy range 60–1332 keV. For minimising the power consumption, the signal processing electronics has been custom designed. This electronics was realised using standard off-the-shelf components to reduce the cost. The developed spectrometer is of size 16 cm × 10 cm × 6 cm, weighs 600 g and consumes 600 mW power. The spectrometer is developed such that it could be directly interfaced with GSM/Xbee for wireless communication with the radiation monitoring networks. The lower-level discriminator threshold of the system is 40 keV and the total electronic noise is <20 keV. The experimentally measured sensitivity of the spectrometer for 137Cs (662 keV) is 2.4 cps/μGy/h at 3.5 V overvoltage. The spectrometer offers excellent linearity over the measured energy range of 60–1332 keV and an energy resolution of ~10% for 662 keV gamma-ray at room temperature. [ABSTRACT FROM AUTHOR]

Surface soil samples were collected from Konya, Turkey and natural activity concentrations were determined using the ɤ-ray spectroscopy system with HPGe detector. The activity concentrations of 226Ra, 232Th and 40K were found to vary from 14.07 ± 0.71 Bq kg−1 dw to 67.27 ± 1.62 Bq kg−1 dw, 10.19 ± 2.60 Bq kg−1 dw to 46.09 ± 0.76 Bq kg−1 dw and 107.87 ± 13.32 Bq kg−1 dw to 605.95 ± 11.34 Bq kg−1 dry weight (dw), respectively. The radiological hazard parameters such as Raeq, D, AEDE, ELCR, AGDE, Hex, Hin, and Iɤ evaluated the radiological risk for the public and environment. The mean values of D, AEDE and ELCR are lower than the world average value of 57 nGy h−1, 70 μSv y−1, 0.29 × 10−3 respectively. The activity concentration distribution maps of 226Ra, 232Th and 40K and the radiological maps of the radiological hazard parameters were plotted using the Surfer programme. Cluster analysis was carried out to indicate the similarity between the variables. [ABSTRACT FROM AUTHOR]

Samples have been collected from two sources of water: drinking water and well water, for various depths for the Al-Bayaa region in Baghdad using a gamma spectrometer with the Germanium HPGe detector. The results of the analysis show that the average activity concentrations were 1.19±0.5 for 238U, 0.96±0.2 for 232Th, and 10.5±0.5 0.5Bq/L for 40K in drinking water samples, and1.77±0.5 for 238U, 1.03±0.2 for 232Th, and 12.6± 0.5Bq/L for 40K in well water samples, respectively. The results were less than their recommended. The study also calculated the radiation hazards represented by the radium equivalent activity, Gamma index, Hazard Index, Absorbed gamma dose rate, Annual effective dose equivalent, and Lifetime cancer risk. All the radiological parameters in water drinking and well samples were within the range of the global limit; thus the water drinking and well water was Safe and free from radioactive contamination in that area. [ABSTRACT FROM AUTHOR]

A new ultra-low background high-purity germanium (HPGe) detector has been installed at the Kamioka underground experimental site. The background count rate in the energy range from 40 keV to 2700 keV is about 25% lower than that of the first HPGe detector installed in 2016, which has the same detector specification and similar shielding geometry. This paper describes the shielding configuration, including the cleaning of the material surface, the comparison of calibration data and simulation, the time variation of the background spectra, the sample measurement procedure, and some results of the radioactivity in the selected samples. [ABSTRACT FROM AUTHOR]

In this study, the specific activities of 226Ra, 232Th and 40K in the unfired construction materials (solid card bricks, 4-hole bricks, pavement bricks) containing fly ash and bottom ash from a coal-fired thermal power plant in Vietnam were measured using the low-level gamma-ray spectrometer with HPGe detector. Also, the 222Rn concentrations in these materials were analyzed using RAD7 radon monitor and then radon mass exhalation rate and emanation fraction of these materials were calculated. The potential radiological hazards for residents living in the model room made of these materials were evaluated. The average specific activity of 226Ra, 232Th and 40K were found as 67.7, 79.3 and 703.5 Bq kg−1, respectively. The total annual effective dose (due to external gamma exposure and internal radon exposure for resident living in the CEN model room made of the unfired brick samples) was found as 0.9 mSv y−1 which is lower than the worldwide average dose of 2.4 mSv y−1. Calculations from ResRad-Build code showed that the doses due to radon exposure account for from 62.3% (at the first year) to 98.8% (at the next 30 years) of the total gamma and radon dose. Under low air exchange to the outside environment, from the 6th year onwards, the total dose may exceed the average dose value from natural radiation exposure sources. [ABSTRACT FROM AUTHOR]

The main goal of the investigation was to reveal the lateral and vertical regularities of element distribution in the elementary landscape-geochemical system (ELGS) type: summit-slope-closing depression. We used an isotope 137Cs as a tracer of migration of chemical elements in soil and vegetation cover. The study was performed in a test site characterizing undisturbed forest landscapes in the Russian zone of the Chernobyl accident. Investigated ELGS was 16-m long with a relative height difference of 1.5 m. Field measurements of 137Cs activity was performed with a 1-meter step by the modified portable gamma-spectrometer Violinist-III (USA). Cs-137 content in moss and soil cores sampled with the same lateral step was determined in the laboratory using Canberra (USA, HPGe detector). The upper soil layer 8-cm thick contained from 70 to 96% of 137Cs, and 89–99% of the total inventory was fixed in the top 20-cm layer. Cs-137 activity in both the soil and moss cover demonstrated a cyclic type of variability, which was described and modeled using Fourier analysis. Correlation between the actual and modeled activity values (r0.01 = 0.868) showed that three main harmonics are sufficient for representative modeling of the observed cycles. We infer that the revealed patterns are characteristic for most of the chemical elements and may be useful for practical purposes. [ABSTRACT FROM AUTHOR]

The precision measurements of U3O8 and Ra(eU3O8) concentrations were evaluated in 23 geological rock samples by high resolution gamma ray spectrometry (HPGe) using two P-type HPGe detectors. The use of Detector 2 (DET2) (GC5019) has increased the sensitivity by a factor of two for both the measurements in comparison to Detector 1 (DET1) (GCD30180). The Minimum Detection Limit (MDL) and Limit of quantification (LOQ) for U3O8 in DET2 has increased significantly because of negligible background counts in 1.001 MeV ϒ energy peak (0.838% gamma yield). The MDL for Ra(eU3O8) measured by 0.609 MeV and 1.760 MeV has not improved significantly due to the high background counts in these energies whereas LOQ has improved appreciably. DET 2 has given higher level of confidence in reporting the analytical results with acceptable repeatability due to the decrease in uncertainty of the measurements. [ABSTRACT FROM AUTHOR]

As the main detector of the Gravitational wave high-energy Electromagnetic Counterpart All-sky Monitor mission (GECAM), the calibration of the energy response and detection efficiency of the gamma-ray detector (GRD) is the main content of the ground-based calibration. This article mainly focuses on the calibration of the energy response and detection efficiency in the 8–160 keV with a refined measurement around the absorption edges of the lanthanum bromide crystal (⁠|$\rm {LaBr_3}$|⁠). The GRD performances for different crystal types, data acquisition modes, working modes, and incident positions are also analysed in detail. We show that the calibration campaign is comprehensive, the detector performance meets the flight requirements, and the calibration results generally agree with simulations as expected. The detector's model was corrected by the ground-based calibration, which led to the establishment of the calibration data base. [ABSTRACT FROM AUTHOR]

Natural radioactivity was measured in samples of pumice used in construction and some other human uses in the Kingdom of Saudi Arabia. The natural radioactivity produced by the elements 238U, 226Ra, 232Th and 40K in the selected samples of pumice was determined by high-resolution gamma-ray spectroscopy using the HpGe detector. The results obtained from this study show that the average values of radioactivity concentrations of the elements 238U, 226Ra, 232Th, and 40K for the pumice are 97.45, 79.03, 73.13 and 521.91 Bq/kg. In this study, we verified the existence of correlations between these radionuclides and the lack of a secular balance of the examined pumice samples. The mean absorbed dose rate regions was calculated to be 103.69 nGy/h, From the results, the average effective internal and external dose and its average value is of 0.13 and 0.51 mSv/y. The equivalent activity of the pumice radium samples, The result of the measurements is that the result of the external and internal risk indicators and the equivalent activity value of all the measured pumice stone samples are within the permissible limits of all the samples measured are within the permissible limits. also the concentrations of the radioactive elements of 238U, 226Ra, 232Th and 40Kwhich were evaluated for the all samples under study. The results obtained from this study were studied with the recommended results internationally. In this study, we used some mathematical equation models to estimate the concentration of 222Rn activity in the air with 226Ra activities. The 226Ra activity range was found from 28.4 to 122.6 and mean 79.03 Bq/kg. That is why it is not recommended to use pumice in building walls and to be exposed to it for long periods. Standard deviation was used for all measurement. [ABSTRACT FROM AUTHOR]

This study measured the activity concentration of natural radionuclides in cooking oil samples by using a high purity germanium (HPGe) detector. The detected average activity concentration of K-40, Ra-226, and Th-232 is 2.68 ± 1.29 Bq kg−1, 0.35 ± 0.15 Bq kg−1, and 0.30 ± 0.12 Bq kg−1, respectively. Moreover, the measured concentrations were used to assess several radiological hazard indices due to ingestion [i.e., annual effective dose (AED), total AED, and excess life cancer risk (ELCR)] by consumers of these cooking oils. Even though the results indicate that their annual values are far below the worldwide permitted levels, it was observed that the radionuclides pose the highest annual effective dose 17.47 µSv y−1 to children (10-15 years old) to (12-17 years old) and that the testes organ receives the highest annual effective organ dose rate (Dorgan) 1.1 μSv y−1 due to ingestion of the cooking oil samples. [ABSTRACT FROM AUTHOR]

Germanium crystals have a dead layer that causes a decrease in efficiency since the layer is not useful for detection but strongly attenuates photons. The thickness of this inactive layer is not well known due to the existence of a transition zone where photons are increasingly absorbed. Therefore, using data provided by manufacturers in the detector simulation model, some strong discrepancies appear by changing the dead layer. Investigations into the Ge detector response functions for gamma rays have been conducted using straightforward physical mechanisms implemented by Monte Carlo simulations. The detector response function feature's most probable interaction mechanisms are described. The Monte Carlo method is applied to simulate the calibration of a HPGe detector in order to determine the total inactive germanium layer thickness and the active volume that is needed in order to study the response function for both types of detectors. Results indicated a strong impact of dead layer variations on the response function of the simulated detectors. [ABSTRACT FROM AUTHOR]

Ionizing radiation (IonR) such as beta and alpha, positrons, X-rays, and gamma rays cause harmful effects on living organisms, especially humans, and they represent a fundamental problem in the modern age. IonR-protecting materials are compulsory to avert this problem. Hence, the development of good performant IonR shields has gained huge interest. In this work, we investigated the radiation shielding peculiarities of Pb-free barium titanium (BT) added with different amounts of M-type hexaferrite (MH). The impact of MH inclusion on the phase, structural, and shielding capacity of BT sample was systematically investigated. PXRD analysis showed that all BT phases crystallized into a cubic structure. SEM images along with elemental mapping revealed the successful formation of (BT-MH) composites. The radiation shielding peculiarities were measured using HPGe detector and three radioactive sources (Co-60, Cs-137, and Am-241). It was found that at 0.6617, 1.173, and 1.333 MeV, the ceramics with higher MH content have higher mass attenuation coefficient values. The MAC values reduce when the energy increases, which indicates that the ceramics have better shielding capabilities against low energy photons. The half value layer results showed that by adding more MH into the ceramic system, more photons are attenuated at that energy, meaning a thinner shield is needed to attenuate half of the incoming photons. We evaluated the radiation shielding efficiency (RSE) and we found that at energy of 0.05954 MeV, BT-MH2 has the highest RSE of 99.836%. [ABSTRACT FROM AUTHOR]