Naturally Occurring Radionuclides in Soil Samples of Bureti Sub-County of Kericho County Kenya

Author(s):  
C K Rotich ◽  
N O Hashim ◽  
M W Chege ◽  
C Nyambura

Abstract The activity concentration of soil samples of Bureti sub-county was measured using thallium-activated sodium iodide detector. To ascertain the level of radiation hazard to the public, gamma radiation dose rates were also estimated. The average activity concentration due to 40K, 226Ra and 232Th for soil samples are 1164 ± 70, 106 ± 8 and 79 ± 5 Bqkg−1, respectively. An average dose rate of 145 ± 10 nGyh−1 was recorded, which is about 2.5 times higher than the world average value of 60 nGyh−1(UNSCEAR). On the other hand, an average outdoor effective dose of 0.35 ± 0.02 mSvy−1 was measured, which is lower than the ICRP safety limit of 1 mSvy−1. This shows that the radiation hazards from naturally occurring terrestrial radionuclides in Bureti is low and therefore human radiation exposure is within the accepted limits.

Author(s):  
Loat Bui Van

We have determined activity concentrations in 33 soil samples collected from Bolikhamxay Province, Laos. The activity concentrations of the natural radionuclides 226Ra,232Th and 40K in soil samples were measured by a gamma spectrometer with a HPGe detector. The average activity concentrations of the natural radionuclides 226Ra, 232Th and 40K are 43.8 ± 5.6, 57.0 ± 7.3 and 426.4 ± 23.1 Bq.kg-1, respectively. The average activity concentrations of 226Ra and 232Th in this work are higher than those of the world average values. Meanwhile, the  activity concentration of 40 K is almost the same of the world average value. The estimated average outdoor annual effective dose (E) and radium equivalent actitvity (Raeq) are 0.17 ± 0.02 mSv.yr-1 and 154.8 ± 16.1 Bq.kg-1, respectively.


2021 ◽  
Author(s):  
Ezekiel Oghenenyerhovwo Agbalagba ◽  
Mohammed S. Chaanda ◽  
Stephen Uloho U. Egarievwe

Abstract This study examined the radioactivity levels of soil samples within selected solid mining sites in Nigeria using high purity germanium (HpGe) detector. Sixty soil samples in all were collected from the ten solid mineral mining sites investigated and six samples were collected as control samples from non-mining environment for analyses. The results of the activity concentration values obtained for 40K, 226Ra and 232Th are 100.22 Bq kg-1, 33.15 Bq kg-1 and 77.31 Bq kg-1 respectively. The 226Ra and 40K activities were found to be within the United Nation Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) acceptable permissible limit, but the 232Th mean value was above the permissible limit of 30 Bq kg-1 for the public. In comparison, 40K, 226Ra and 232Th soil samples mean activity concentrations were higher than the control soil samples values by 48.6%, 43.7% and 62.3% respectively. The results of estimated radiation hazard indices indicate average values of 150.72 Bq kg-1, 68.40T, 83.65µSvy-1 and 454.70µSvy-1 for the Radium Equivalent (h), iDose Equivalent (AEDE) and Annual Gonadal Equivalent Dose (AGED) respectively. The mean values for External Hazard Indices (Hex, Hin), Representative Gamma index (s) and Excess Life Cancer Risk (ELCR) were 0.41, 0.50, 1.06 and 0.29 x10-3 respectively. The statistical analysis shows positive skewness.


Author(s):  
P. K. Manigandan ◽  
K K Natrajan

Assessments of naturally occurring radionuclides in soil collected from a tropical rainforest forest of western Ghats, India were conducted. These radionuclides were distributed unevenly in the forest soil. For all soil samples, the terrestrial gamma dose rate and the corresponding outdoor annual effective dose equivalents were evaluated. The activity concentration of 232Th and average outdoor gamma dose rates were found to be higher than the global average which appears to affects Western Ghats environment in general, the radiological hazard indices were found to be within the International Commission on Radiological Protection recommended limits. Hence, obtained results for natural radionuclides in the forest soils were within the range specified by UNSCEAR (2000) report for virgin soils except 232Th.


2021 ◽  
pp. 3911-3920
Author(s):  
Mahdi Hadi Jasim ◽  
Afrah Essa Ramadan ◽  
Nessrian Ali Hussain

Purification of fifteen NaCl samples from natural and different area in the middle and south of Iraq are prepared  and studied the structural characteristics of samples by powder X-ray diffraction analysis at 𝛌=1.542Ã…. The present work considered the specific activities of naturally occurring radioactive materials in salt samples, which are measured and analyzed using high resolution HPGe system. Also, the radiological parameters have been considered in this work. The average specific concentration (in Bq.kg-1) of the salt samples is found 16.864.92 for 226Ra, 5.972.05 for 232Th and 9.852.8 for 40K, respectively, which are below the national levels, 40Bq.kg-1, 30Bq.kg-1 and 400Bq.kg-1, respectively (UNSCEAR, 2000). Similarly the absorb dose rates are in the range3.71 nGy.h-1 to 12.591nGy.h-1.The measured radiation hazard indices show that the concentrations of these radionuclides in all samples are within the allowable limits.


Author(s):  
R. Barthel ◽  
W. Goldammer ◽  
M. Helming

Abstract The new German Radiation Protection Ordinance contains for the first time a systematic framework of regulations protecting workers and the public against radiation exposures from residues of industrial and mining processes containing enhanced levels of naturally occurring radionuclides (TENORM). These regulations will satisfy the requirements of the European Council Directive 96/29/EURATOM and serve as a common basis for the radiation protection activities of the German states in this field. The consideration of exposures from materials containing naturally occurring radionuclides gains on this basis an increased level of significance within the German radiation protection efforts. The overall goal of the new regulations is to keep the additional effective dose for the population from the recycling and disposal of TENORM below 1 mSv/a. In order to achieve this objective, companies in which such residues arise have to carry out representative measurements of activity concentrations in these materials. If exemption levels defined in the new regulations are exceeded, restrictions on the recycling and disposal come into effect. These exemption levels are nuclide specific and distinguish between material types and different recycling and disposal options. This specific definition of exemption criteria serves the goal to minimise the number of companies and the amount of residues affected by the new regulations to the extent possible, focussing the efforts of operators and regulators to those materials having the potential to actually cause radiation exposure problems. The specific exemption criteria were derived on the basis of an analysis of typical amounts and activity concentrations of industrial and mining residues with enhanced radioactivity contents in Germany. In a second step, practically applied options for the recycling and disposal of these materials were investigated. On this basis, generic scenarios for the radiation exposure of the workforce and the public were defined and doses were estimated. All relevant pathways including possible long term effects (ground water) were considered in these analyses. Based on the 1 mSv/a criterion, a catalogue of relevant materials, potentially requiring radiation protection measures, was developed. For these materials the practically applied recycling or disposal options were grouped into categories, for which specific exemption levels were derived. The derivation of these criteria was based on realistic estimates of radiation exposure, for example taking into account the dilution of the residues with other materials in technological processes or during the disposal in landfills. The residues subject to the new regulations mostly arise in large quantities over extended periods of time. This leads to significant variations of radionuclide concentrations depending on feed materials and process parameters. To carry out representative measurements without the necessity of taking a too large number of samples, therefore, requires an adequate measurement strategy. Particular aspects to be considered are uncertainties of the measurements themselves and the heterogeneity of the residues. In addition, the measurement strategy has to be compatible with diverse situations in the different industries affected. The framework developed for designing individual strategies for the various industries and types of residues satisfies these requirements and can also provide guidance for measurement campaigns in other areas. The paper outlines the general situation with regard to TENORM in Germany. The main streams of residues and options for their recycling or disposal are described. On this basis, scenarios used for the radiological evaluation are defined and examples for resulting radiation exposures are given. The exemption levels derived from this analysis are discussed. Finally, the framework for the design and implementation of an adequate measurement strategy is outlined.


Author(s):  
Soja Reuben Joseph ◽  
Juyoul Kim

Various products containing a small number of added radionuclides are commonly available for use worldwide. However, frequent use of such products puts the public at risk of radiation exposure. In this study, dose assessments to members of the public using consumer products containing naturally occurring radioactive materials (NORMs) were conducted for various usage scenarios to evaluate the external and internal exposure dose. Data for this study were obtained from previous literature and were statistically analyzed using Boxplot to determine the input data for assessment. A normalized value of activity concentration was used for dose evaluation. In addition to other external and internal dose calculation codes, analytical calculations were used to perform age-dependent. Based on analytical calculations, the highest total effective dose equivalent (TEDE) received from necklace products at the upper whiskers with an activity concentration of 4.21 Bq/g for 238U, 24.4 Bq/g for 232Th, and 0.55 Bq/g for 40K for various age groups is 2.03 mSv/y for 1 year old, 1.24 mSv/y for 10 years old and 1.11 mSv/y for adult, which are above the international commission for radiation protection (ICRP) recommended public dose limit of 1 mSv/y. Results of external and internal exposure dose obtained using Microshield code, IMBA code and Visual Monte Carlo (VMC) code are all below the recommended public dose limit of 1 mSv/y.


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