Hyper Pure Germanium Detector Research Articles

Polyurethane reinforced with micro/nano waste slag as a shielding panel for photons (experimental and theoretical study)

This study not only provides an innovative technique for producing rigid polyurethane foam (RPUF) composites, but it also offers a way to reuse metallurgical solid waste. Rigid polyurethane (RPUF) composite samples have been prepared with different proportions of iron slag as additives, with a range of 0–25% mass by weight. The process of grinding iron slag microparticles into iron slag nanoparticles powder was accomplished with the use of a high-energy ball mill. The synthesized samples have been characterized using Fourier Transform Infrared Spectroscopy, and Scanning Electron Microscope. Then, their radiation shielding properties were measured by using A hyper-pure germanium detector using point sources 241Am, 133 BA, 152 EU, 137Cs, and 60Co, with an energy range of 0.059–1.408 MeV. Then using Fluka simulation code to validate the results in the energy range of photon energies of 0.0001–100 MeV. The linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer and tenth-value layer, were calculated to determine the radiation shielding characteristics of the composite samples. The calculated values are in good agreement with the calculated values. The results of this study showed that the gamma-ray and neutron attenuation parameters of the studied polyurethane composite samples have improved. Moreover, the effect of iron slag not only increases the gamma-ray attenuation shielding properties but also enhances compressive strength and the thermal stability. Which encourages us to use polyurethane iron-slag composite foam in sandwich panel manufacturing as walls to provide protection from radiation and also heat insulation.

Natural and Artificial Radionuclides Distribution in Surface Soil in Baghdad International Airport Region

This is the first time that radiological assessment achieved in the Baghdad International Airport (BIA) in Iraq. Twenty-three sites were sampled from upper 5 cm of the surface soil within the BIA to be analyzed for the radioactivity of natural radionuclides Ra-226, Th-232 and K-40 and the artificial radionuclide, Cs-137 using gamma spectroscopy based on Hyper pure Germanium detector (HPGe). Ten samples out of the 23 samples were analyzed for U-238, U-235 using the Neutron Activation Analysis method. To determine the percentage of DU [DU (%)] which is calculated from the 235U/238U isotope ratio. The study showed that there is a possibility of slight contamination with depleted uranium in two sites out of the 23 sites that were examined. The average activities of Ra-226, Th-232, and K-40 in the study area are within the limits of world averages, while there are evidences that new feeding of Cs-137 in the region, reaches about 19 Bq/kg, from the new global fallout after Chernobyl accident. The measured and calculated absorbed doses in the study area were within international limits and no need for farther monitoring. Annual effective dose equivalent due to resuspension of Ra-226 is estimated to be 1.0E-10Sv, and this value is negligible compared with 1 mSv permissible value for public recommended by ICRP.

NATURAL RADIOACTIVITY LEVELS AND RADIOLOGICAL HAZARDS INDICES OF SOIL SAMPLES FROM SELECTED MINING SITES, DANGE-SHUNI, SOKOTO STATE, NIGERIA

Elevation of environmental radioactivity is a growing concern that requires monitoring and measurement via nuclear analytical procedures and have been conducted from Dange-Shuni in this study. The unabated mining activities whose motive is to constantly keep industries running on locally sourced minerals and raw materials often leave the host communities with heavy burden of radioactivity impacts that have be monitored in this study. this should explicitly and clearly state main objectives of the work. Hyper Pure Germanium detector coupled to a Multi-Channel Analyzer (MCA) was used for gamma-ray spectrometry to ascertain the activity concentration results of ,,in 15 packs of homogenized soil samples collected from mining sites, Dange-Shuni LGA, Sokoto State, Nigeria. Mutually exclusive and collectively exhaustiveness approach of sampling was adopted in order to overcome the limitations of large and diverse nature of mining localities terrain. Results obtained from gamma-ray spectroscopy reveals a range of 30.72.9 to 95.67.2, 30.72.9 to 95.67.2 and 499.2051.5 to 971.2421.5 for ,and respectively. The mean values were calculated to be 58.04, 54.5 and 767.62 respectively. The radiological hazards of , , , , , and were obtained for the results of activity concentration ascertained in this study. The results were found in elevations to the world mean values in comparison which is an implication of dangers of environmental radioactivity to the generality of the dwellings. These results are in good agreements with previous studies and hence, suggests for similar investigation to be conducted.

Radiological assessment of different monazite grades after mechanical separation from black sand

In Egyptian black sands, monazite is a precious mineral characterized by its composition, which includes crucial constituents such as thorium, trace amounts of uranium, and rare earth elements. It is essential to evaluate and quantify the extent of gamma-ray exposure resulting from the presence of primordial radionuclides. This necessity arises from human activities that extract and retrieve raw materials in uranium and thorium mining operations. The current study focuses on the radiological assessment of Monazite raw material in various grades and calculates the associated hazard indices. A hyper pure Germanium detector (HPGe) determined the particular activity. For grade, 90% Monazite samples, the average activities for 232Th, 238U, and 40K were 348,008 ± 1406, 69,299 ± 2086, and 27,510 ± 245 Bq/kg, respectively. For grade 75% Monazite samples, the average activities were 219,000 ± 901, 55,000 ± 500, and 18,300 ± 86 Bq/kg, while for grade 50% Monazite samples, it was 43,294 ± 1549, 9593 ± 629, and 4000 ± 211 Bq/kg for the same element, respectively. Also, 138La’s inherent radioactivity was taken into account. The computed effective and absorbed dosages exceed the worker’s exempt limit of 20 mSv/y. The calculated hazard parameters are higher than the maximum recommended limits. Therefore, it is imperative to employ radiation safety measures to mitigate the potential hazards of ionizing radiation.

Assessment of Radium Equivalent Activity and Total Annual Effective Dose in Cassava cultivated around Ewekoro Cement Factory

In this study, cassava tubers cultivated in the Ewekoro cement area were investigated with the aid of Hyper Pure Germanium (HPGe) detector in order to assess the radionuclide content. Twenty-seven (27) samples of both arable soil and cassava tubers were studied at different sites to the epicenter of the mining activity. The results revealed the highest activity concentrations of K-40, Ra-226, and Th-232 to be 194.10, 63.92, and 76.90 Bq/kg, respectively, in soil to be at site 1, which was 50 m away from the cement mining site. Similarly, cassava reported the highest activity concentrations of 228.15 and 81.50 Bq/kg for K-40 and Ra-226, respectively, at sites 2, which was 150 m away from the mining site. However, the highest value of Th-232 in cassava was noted in site 1. Also, the highest values of Raeq for arable soil and cassava tubers were estimated to be 188.84 Bq/kg and 199.89 Bq/kg at site 1 and site 2, respectively. All the above results were higher than the recommended safe limits by a factor of 2. Moreover, the Total Annual Effective Dose of exposure by oral ingestion of cassava tubers for different age groups revealed children to have the highest level of exposure with the highest mean value of 7.98 mSv. This is followed by adults and infants, which reported 5.66 and 5.38 mSv, respectively, all at site 2. This result is far greater than the recommended safe limits of 1 mSv. Therefore, the results of the total averages of annual effective doses due to consumption of the three natural radionuclides in cassava tubers and other products from it by adults, children, and infants were found to be above the average annual ingestion radiation dose due to natural sources. Further statistical analysis of the results showed significant differences between sites 1 and 2 and between sites 1 and 3, where there was no statistically significant difference between sites 2 and 3.

Radiometric analysis of Brazilian commercial ornamental stones

The term “commercial ornamental stones” comprises different natural stones with different mineralogical components and the distribution and amount of natural radionuclides depended on the mineralogy. Few studies on natural radioactivity in ornamental stones carried out in Rio de Janeiro (Brazil) and the present work were carried out in order to analyze the distribution of activity concentration in these materials. The activity concentration of 238U, 235U, 226Ra, 232Th and 40K in Ornamental Stones measured using γ-ray spectrometry to estimate the radiation hazard as well as establishing a database for radioactivity levels. Samples were collected in stores in Rio de Janeiro, carefully transported, weighed, packed with PVC film and left to rest for at least 45 days to reach secular equilibrium. Samples analyzed by gamma spectrometry using a hyper pure germanium detector (HPGE). Detection efficiency for each sample was obtained using LabSOCS software. The activity concentrations for samples were within the ranges (0.83 ± 0.15 to 39.96 ± 1.19, 8.04 ± 2.54 to 111.36 ± 13.33, 0.43 ± 0.03 to 264.58 ± 0.98, BDL to 8.17± 0.65 and 1.30 ± 0.57 to 1567.01 ± 65.08) Bq⋅kg−1 for 238U, 226Ra, 232Th, 235U and 40K, respectively. The world average for building materials is 50 Bq⋅kg−1 for 238U, 50 Bq.kg−1 for 232Th and 500 Bq⋅kg−1 for 40K. In the present work, the average for granite was 19.43 ± 0.39 Bq⋅kg−1 for 238U, 56.70 ± 1.13 Bq⋅kg−1 for 232Th and 1113.28 ± 20.27 Bq⋅kg−1 for 40K, thus the values for 232Th and 238U are above the world average. Analyzing for the granite that showed the highest concentrations of activity the average values of Transport Rate was 3.12 ± 0.04 Bq⋅m−2⋅s−1, Emanation Rate was 0.16 ± 0.00 Bq⋅kg−1⋅s−1, Exhalation Flow was 530.26 ± 6.05 Bq⋅m−3, Effective Equivalent Dose Due to Radon Exposure was 0.78 ± 0.01 WLM⋅year−1 and Annual Effective Dose Due to Radon and Thoron was 7.02 ± 0.10 mSv⋅year−1. Annual Effective Dose Due to Radon and Thoron it is above the annual limit for public individuals which is 1 mSv⋅year−1 and below the occupationally exposed individual, which is 20 mSv⋅year−1 in an average of 5 years, it does not exceed the maximum level recommended by ICRP-60.

Advancements in Thermoluminescence Dating: A Case Study of Medieval Brick Structures in Azerbaijan

The study aimed to improve the precision of dating historical landmarks, specifically the Ballabur castle in Lenkaran, Azerbaijan Republic, using the thermoluminescence dating (TL) method. The annual dose rate, calculated with a -spectrometer equipped with a hyper-pure germanium detector, was found to be 2.98±0.19 mGy/year. By employing an online dose rate and age calculator, the sample's age was determined to be 920±50 years, consistent with the historical estimates of this region.
 

Natural Radioactivity and Associated Radiation Hazards in Samples of Maize Available to the People of KwaZulu-Natal, South Africa

Ingestion of foods and drinking water is considered the leading cause of human exposure to radioactive elements that guide to internal radiation doses. The concentrations and distributions of natural radionuclides 238U, 232Th, and 40K in samples of yellow maize directly consumed in the KwaZulu-Natal province of South Africa were determined to estimate possible radiological hazards to human health. Representative samples collected from towns in six regions of the province were analyzed using a Canberra-supplied broad energy hyper pure germanium (HPGe) detector. The mean activity concentrations were 21.3, 26.0, 21.0, 52.0, 53.3, and 80.7 Bq/kg for 238U, and 203.3, 386.7, 183.3, 336.7, 320.0, and 526.7 Bq/kg for 40K. 232Th was not detected in any of the maize samples from the studied locations. The estimated effective ingestion doses and the lifetime cancer risks due to 238U and 40K were within internationally recommended limits of 1 mSv and 10–3 for members of the public. However, the values obtained seem high in some locations, particularly for a single diet intake. This finding is part of the radiological baseline information of the KwaZulu-Natal province and, in general, South Africa from maize consumption.

Natural Radioactivity and Associated Radiological Hazard Indices in Carbonatite Rocks from Oldoinyo Lengai, Tanzania

The distributions of naturally occurring radionuclides 232Th, 238U and 40K in carbonatite rocks from Oldoinyo Lengai region, Tanzania were determined. The Hyper-pure Germanium (HPGe) detector based on gamma spectroscopy located at Tanzania Atomic Energy Commission (TAEC) in Arusha was used in order to assess the radiological health hazards associated with the use of carbonatite rocks. The mean activity concentrations of 232Th, 226Ra and 40K were found to be 51.75 Bq/kg, 46.38 Bq/kg and 966.56 Bq/kg respectively. The results of mean activity concentration together with radiological hazard indices obtained in this study were all higher than their worldwide maximum recommended limits. This indicates that there exist radiation risks within the vicinity of carbonatite deposits in Oldoinyo Lengai. The region is known to be subjected to environmental degradations due to volcanic activities. Therefore, findings in this study could also serve as an important radiometric baseline data upon which future epidemiological studies and environmental monitoring initiatives could be based.

Counting efficiency in gamma-ray spectrometry with different sample volumes for the same geometry

The aim of this study is to determine an easy and fast method to calculate efficiencies in different volumes, in the same counting geometry, for gamma-ray spectrometry technique. Reference Material Soil IAEA 326 was packed in a 100 mL capacity polyethylene bottle with different masses and volumes, and sealed for about four weeks, prior measurement, in order to ensure that radioactive equilibrium had been reached between 226Ra and its progeny. After this time, they were measured by gamma-ray spectrometry with a hyper-pure germanium detector. The masses of the reference material used were 25, 60, 80, 95 and 128g. The energies of gamma-rays used in this paper are recommended due to the considerations: gamma intensity value, peak quality, spectral region without interference and the gamma- ray energies of the 238U and 232Th series very important for determining the natural radioactivity. The efficiency values obtained compared to the adjusted efficiency values were similar and presented a good correlation coefficient. The performance was acceptable for all different masses studied, indicating results consistent for the method. The proposed method could be useful as a tool for laboratories, dealing with of samples on a routine basis, by reducing the cost on the purchase of another counting geometry and optimizing the use of the detection system, thus improving their performance.

A Technique of Efficiency Calibration of HPGe Detector

In this work, a technique for the determination of efficiency calibration of hyper-pure germa-nium detector was obtained using four different concentrations of KCl in Bq/l for different
 geometrical configurations. The relative intensities of Gamma-rays from 226Ra with its Gamma-Emitting daughters were used in addition to the normalizing factor relative to the intensities of
 gamma-rays photo peaks. The results of this method were compared to standard samples ofIAEA-373 and they were found to be in good agreement.

Evaluation of linac-based delayed gamma neutron activation technique for copper characterization in scrap metal by means of Monte Carlo modeling

Delayed gamma rays following neutron activation, induced by a 6 MeV linear electron accelerator (linac) coupled to a deuterium oxide photo–neutron conversion target, are simulated with MCNP6.1. The 1039 keV copper activation gamma peak is detected with a 33% relative efficiency hyper pure germanium detector. Two copper distributions were assessed for a 2-hour irradiation followed by a 2-hour counting configuration. Homogeneously distributed copper in a planar scrap metal matrix shows 65Cu detection limits of 10.01 g. A solid copper sample, modeled at five distinct positions in the planar scrap metal matrix, exhibits detection limits from 8.27 to 14.27 g.

Towards the Reliability Check of Complementary Methods for the Precise Estimation of Peak Efficiency of a Long Run Used Germanium Detector in Low Activity Environmental Measurements

The gamma-ray spectrometry using long run used hyper pure germanium (HPGe) detector needs a stringent full energy peak (FEP) efficiency calibration for environmental radioactivity measurements. The FEP efficiency calibration was carried out using the complementary methods like analytical estimations and Monte Carlo (MC) simulations. In our work, for the analytical estimations, the relative deviation of the theoretical results with that of experimental FEP efficiency was found to be less than 6%. However, in the case of MC methodologies, an overall estimated standard deviation of 5% could be achievable only with the optimized geometry of the long run used germanium detector for low-activity environmental measurements.

Assessing the need for radiation protection measures in artisanal and small scale mining of tantalite in Oke-Ogun, Oyo State, Nigeria

There is concern that work scenarios on the tantalite mining sites in Oke-Ogun, Oyo State, Nigeria may cause occupational radiation exposure of workers due to enhanced concentrations of naturally occurring radionuclides in some process materials. A prior radiological assessment of the mining activities was carried out to determine if and which exposure scenarios may require radiation protection measures. Samples of the materials involved, comprising tantalite (tantalum ores), soil and waste rock were collected and analyzed for activity concentrations of 40K, 226Ra, 238U and 232Th using a hyper pure germanium detector gamma-ray spectrometer. Radon concentrations in the mines were also measured using a continuous radon monitor - Radon-Scout Plus (Sarad, GmbH). Activity concentrations of 40K are below 10 Bqg-1 in all the samples but all the tantalite samples contain more than 1 Bqg-1 of 226Ra and 238U. Hence tantalite is regarded as naturally occurring radioactive material (NORM) and the mining activity as a practice. The requirements for planned exposure situations apply to all the mining sites but, on the basis of graded approach, the optimum radiation protection measures vary from one mine to another, ranging from exemption to authorization. Exposures to radon in the underground mines pose the greatest radiological risks and portend the greatest need for regulatory control in the mining operations. The results further underscore the need to integrate radiation protection with the other health and safety measures in the mining sector.

Assessment of radiological health risk and radiogenic heat production changeability of different sedimentary rocks at Gabal Um Hamd, Southwestern Sinai, Egypt

Soil is a source of natural radionuclides and a source of natural radiation risk to humans. This study aims to measure the radioactivity concentrations, contributions, radiological hazards and to quantify the radiogenic heat productions in thirty two rock samples having different lithology from the middle member of Um Bogma Formation in Gabal Um Hamd, southwestern Sinai, Egypt. The concentration of natural radionuclides was determined using a p-type Hyper Pure Germanium (HPGe) detector. The average activity concentrations of uranium thorium and potassium in the interested area were found to be 4909.58 ± 54.34 5003.12 ± 17.56 79.04 ± 8.82 and 137.35 ± 8.64 respectively. Other hazard indices average values were measured, such as: annual effective dose equivalent, radium equivalent activity, external and internal indices, annual gonad equivalent dose, and excess lifetime cancer risk. The radiologic hazards results, obtained in this study shows that the radiation levels are higher than the internationally approved values and the recommended safety limits. Furthermore, the results show that the radiogenic heat value ranged from 3.58 to 402.45 μW m −3 with an average value of 60.11 ± 0.79μW m −3 in the studied area which is higher than previously reported averages.

Radiological hazard assessment and sensitivity analysis for soil samples in Taghdoua area of Ranyah, Saudi Arabia

In this study, twenty-two samples of soil were studied for 222Rn, 226Ra, 232Th and 40K using hyper-pure Germanium (HPGe) detector. The soil samples were collected from an inhabited area surrounding the small mountain in Taghdoua area of Ranyah. The measured activity concentrations of 226Ra, 232Th and 40K in the soil were found to vary from 6 to 54, 7 to 52 and 299–761 Bq kg−1, respectively. The radiological risk parameters including excess lifetime cancer risks and other relevant parameters were also evaluated. Furthermore, the effect of ventilation changes on both external and internal doses over a protracted exposure duration were studied through sensitivity analysis using RESRAD-BUILD computer code. The external doses were observed to be insensitive to ventilation while a considerable change was detected in the internal doses with ventilation. Hence, the investigated radiological risk parameters including the results from RESRAD were all below the recommended limit.

Spatial Distribution of Radiometric and Dosimetric Parameters in Soil Samples from Selected Areas in Bayelsa State, Nigeria

Radiation from radioactive materials/radionuclides in the environment enhanced by anthropogenic activities is presently of a great concern globally. The objective of this study is to determine the radiometric and dosimetric parameters from soil samples collected randomly from the study area of Bayelsa State, Nigeria. The samples were prepared using standard methods and analyzed with a high resolution Hyperpure Germanium Detector configuration (HPGe). The results showed the clay samples to have higher activity concentration to the sands samples with activity concentration of clay samples ranging between 68.99±9.05 –189, 42±21.11Bq/kg and the sand samples with activity concentration range of 17.95±5.87 – 38.59±7.43Bq/kg. The activity concentration spatial distribution map in clay lithologies showed 2 peak values trending north-west, while the sand lithology showed a single peak central distribution. The result also showed the values of the absorbed doses with the 8 clay samples values ranging between 59.09 - 155.25nGy/h and sand samples values between 17.90 – 33.92nGy/h. The spatial distribution of the dose showed 2 peak central distribution in clay samples and north-east trending distribution of high peak values for samples with sand lithologies. In addition, the results showed an effective absorbed dose of range of 0.235-0.0616mSv/y for samples with clay lithology and 0.0071-0.0135mSv/y for samples with sand lithology The activity concentration of all the samples studied are below the 1000Bq/kg international reference limit for Radium 226, Thorium 232, uranium 238 and 10,000Bq/kg for potassium 40. The absorbed dose rate and annual effective absorbed dose are also below the international reference limits published by ICRP, 2007 and UNSCEAR, 2000 publications. Also, effective activity maximum limit of 370Bq/kg for input raw materials for public building is not exceeded.

Risk Assessment of Natural Radionuclides and Radon Gas in the Artisanal and Small-Scale Gold Mine of Buhemba, Tanzania

Currently, the mining industry in Tanzania faces significant challenges including the presence of radionuclides in the working environment. In this work, different indices were applied to assess the health risk of people living and working in the study area. The radiation hazards in the studied mining areas are compared with the recommended local and international guidelines. The health risk and mitigation measures due to radioactive elements exposure to mine workers and people dwelling in the mines is established. The hyper pure germanium detector (HPGe) was used for radioactivity analysis. The radon gas levels were measured using the Alpha Guard radon monitor. The results on radioactivity; mean effective dose; annual gonadal equivalent and absorbed dose; radium equivalent; internal and external hazard indices; alpha and gamma indices; and the radon gas revealed high values in mining areas compared to the control area. However, some of the levels of radionuclides along with their hazard indices are lower than the recommended international limits. The mitigation measures which include dust suppression using water spray and the use protection gears such as masks and gloves are recommended. The present study recommends follow up and further studies in the ASGM subsector.

Investigation of Radioactivity Levels and Lead in Soil and Shore Sediment from Port Said, Egypt

Soil is one of the foremost vital foundations of life for humans, animals, and plants, so the soil contamination by radionuclides is a dangerous threat of human health. This study investigated the ²²⁶Ra, ²²⁸Ra, ⁴⁰K, ¹³⁷Cs and pb to assess their risks in soil cover of Port Said governorate. So, 41 samples (29 soil samples and 12 shore sediment samples) were collected to cover the districts area, beaches and industrial areas in Port Said governorate. Activity concentrations of ²²⁶Ra, ²²⁸Ra, ⁴⁰K and ¹³⁷Cs were determined by Hyper-Pure Germanium detector, and their Pearson’s coefficient correlations were calculated and to assess the effects of radiation produced from these radionuclides, their hazards indices were estimated. Pb was determined using Ionized coupled plasma optical emission spectroscopy (ICP-OES), Geo-accumulation index (I-geo) and Contamination Factor (CF) were calculated. The activity concentration of soil for ²²⁶Ra, ²²⁸Ra, ⁴⁰K and ¹³⁷Cs ranged from 2.78 to 26.88, BDL to 19.69, BDL to 382.34 and BDL to 1.14 Bq/Kg with average values 11.59, 7.53, 218.77 and 0.25 Bq/Kg respectively. The activity concentrations of shore sediment for ²²⁶Ra, ²²⁸Ra, ⁴⁰K and ¹³⁷Cs ranged from 5.48 to 15.17, BDL to 11.75, BDL to 448.48 and BDL to 1.14 Bq/Kg with average values 10.16, 6.91, 364.23 and 0.38 Bq/Kg respectively. The highest activity concentrations and values of hazard indices are around the industrial facilities in both cases of soil and shore sediment samples as a result of contamination from factories. But the average activity concentration of ²²⁶Ra, ²²⁸Ra, and ⁴⁰K in the soil and shore sediment samples are still lower than the worldwide activity concentrations average values and the Egyptian activity concentrations mean values. Also, all values of hazard indices and their average values are below recommended values by UNSCEAR 2000. Geo-accumulation Index (I-geo) and Contamination Factor (CF) for Pb indicated that more than 2 thirds of soil and 80% of shore sediment samples are moderately polluted or considerably contaminated by Pb. Pearson's Correlation indicated that pb from side and ²²⁶Ra, ²²⁸Ra and ⁴⁰K from other side may be from different sources.

Proposal to correct for the effect of background and density in the determination of gamma emitters using sodium iodide detectors

This study develops a modification to the spectra decomposition method for sodium iodide scintillation equipment, including correcting the natural background counts for the activity concentration calculation. A comparison of the results obtained between two sodium iodide detectors of 2 X 2 in and 3 x 3 in versus a hyper-pure germanium detector of 50 % relative efficiency is performed for soil, sediment, and water samples. It is found that background correction significantly improves activity concentration results in higher energy regions. The concentration values determined by the different spectrometric systems for the samples analyzed do not show significant differences, which supports the results obtained with the proposed calculation method. The uncertainty associated with the measurement and detection limits for the NaI (Tl) detectors is higher than those obtained with the GeHp detector due to the operation of the two technologies and the presence of interferences in the regions of interest. The study carried out in this work establishes an analytical milestone. The methodological model proposed makes it possible to quantify, with reliable results, low concentration levels of NORM materials and even 131I using sodium iodide detectors, among other analytical applications of general interest.