EFFECT OF BUILDUP FACTORS ON INDOOR GAMMA DOSE RATE

2020 ◽  
Vol 190 (2) ◽  
pp. 132-138
Author(s):  
V Manić ◽  
G Manić ◽  
D Nikezić ◽  
D Krstić
Keyword(s):  
Effective Dose ◽  
Dose Rate ◽  
Gamma Rays ◽  
Building Materials ◽  
Absorbed Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Absorbed Dose Rate ◽  
Dose Rates ◽  
Buildup Factors

Abstract The effect of buildup factors on absorbed dose rate in air and the effective dose from gamma rays of primordial radionuclides in building materials, was investigated in the article. Specific absorbed dose rates were calculated for the standard concrete room, as well as, for rooms where brick and covering building materials were used. For all room models the Harima (G-P) buildup factors were applied, while for the standard room the Berger’s and Taylor’s buildup factors were used, too. The contribution of the radiation buildup to absorbed dose rate and effective dose was determined as large as 41%.

scholarly journals 232Th, 226Ra, and 40K activities and associated radiological hazards in building materials of Islamabad capital territory, Pakistan

2012 ◽  
Vol 27 (4) ◽  
pp. 392-398 ◽  
Author(s):  
Saeed Rahman ◽  
Muhammad Rafique
Keyword(s):  
Effective Dose ◽  
Dose Rate ◽  
Building Materials ◽  
Annual Effective Dose ◽  
Absorbed Dose ◽  
Absorbed Dose Rate ◽  
Radium Equivalent Activity ◽  
Radiological Hazards ◽  
Radium Equivalent ◽  
The Mean

Radioactivity levels in building materials, collected from the Islamabad capital territory have been determined by using a gamma spectrometric technique. Measured specific activities of 226Ra, 232Th, and 40K in material samples ranged from 8 ? 1 to 116 ? 6 Bq/kg, 9 ? 1 to 152 ? ? 5 Bq/kg, and 29 ? 6 to 974 ? 23 Bq/kg, respectively. The radium equivalent activity, absorbed dose rate, annual effective dose, and gamma index were evaluated from the measured amounts of radioactivity to assess the radiation hazard associated with the studied building materials. The mean radium equivalent activity, the absorbed dose rate and annual effective dose estimated ranged from 81 ? 6 to 221 ? 11 Bq/kg, 38 ? 3 to 104 ? 5 nGy/h, and 0.23 ? 0.02 to 0.64 ? 0.03 mSv, respectively. The ranges of the calculated Raeq were found to be lower than the values recommended for construction materials (370 Bq/kg). The mean values of the internal and external hazard indices were found in the range of 0.30 ? 0.02 to 0.78 ? 0.05 and 0.22 ? 0.02 to 0.60 ? 0.03, respectively. The results of the materials examined indicate no significant radiological hazards arise from using such material in building construction.

scholarly journals The dose of gamma radiation from building materials and soil

Nukleonika ◽  
2015 ◽  
Vol 60 (4) ◽  
pp. 951-958 ◽  
Author(s):  
Goran Manić ◽  
Vesna Manić ◽  
Dragoslav Nikezić ◽  
Dragana Krstić
Keyword(s):  
Gamma Radiation ◽  
Effective Dose ◽  
Building Materials ◽  
Absorbed Dose ◽  
Published Data ◽  
Dose Rates ◽  
Construction Products ◽  
Conversion Coefficients ◽  
Hpge Gamma Spectrometry ◽  
Buildup Factors

Abstract The radioactivity of some structural building materials, rows, binders, and final construction products, originating from Serbia or imported from other countries, was investigated in the current study by using the standard HPGe gamma spectrometry. The absorbed dose in the air was computed by the method of buildup factors for models of the room with the walls of concrete, gas-concrete, brick and stone. Using the conversion coefficients obtained by interpolation of the International Commission on Radiobiological Protection (ICRP) equivalent doses for isotropic irradiation, the corresponding average indoor effective dose from the radiation of building materials of 0.24 mSv·y−1 was determined. The outdoor dose of 0.047 mSv·y−1 was estimated on the basis of values of the specific absorbed dose rates calculated for the radiation of the series of 238U, 232Th and 40K from the ground and covering materials. The literature values of the effective dose conversion coefficients for ground geometry were applied as well as the published data for content of the radionuclides in the soil.

scholarly journals Correlation analysis of gamma dose rate from natural radiation in the test field

2016 ◽  
Vol 31 (3) ◽  
pp. 260-267 ◽  
Author(s):  
Senada Avdic ◽  
Beco Pehlivanovic ◽  
Mersad Music ◽  
Alma Osmanovic
Keyword(s):  
Correlation Analysis ◽  
Dose Rate ◽  
Absorbed Dose ◽  
Soil Samples ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Spectrometric Analysis ◽  
Test Field ◽  
Absorbed Dose Rate ◽  
Narrow Energy Range

This paper deals with correlation analysis of gamma dose rate measured in the test field with the five distinctive soil samples from a few minefields in Federation of Bosnia and Herzegovina. The measurements of ambient dose equivalent rate, due to radionuclides present in each of the soil samples, were performed by the RADIAGEMTM 2000 portable survey meter, placed on the ground and 1m above the ground. The gamma spectrometric analysis of the same soil samples was carried out by GAMMA-RAD5 spectrometer. This study showed that there is a high correlation between the absorbed dose rate evaluated from soil radioactivity and the corresponding results obtained by the survey meter placed on the ground. Correlation analysis indicated that the survey meter, due to its narrow energy range, is not suitable for the examination of cosmic radiation contribution.

REDUCTION IN AMBIENT GAMMA DOSE RATE FROM RADIOCESIUM DUE TO SNOW COVER

2019 ◽  
Vol 184 (3-4) ◽  
pp. 510-513
Author(s):  
Y Omori ◽  
S Inoue ◽  
T Otsuka ◽  
Y Nagamatsu ◽  
A Sorimachi ◽  
...  
Keyword(s):  
Snow Cover ◽  
Dose Rate ◽  
Gamma Rays ◽  
Snow Water Equivalent ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Dose Rates ◽  
Gamma Dose Rates ◽  
Snow Water ◽  
Ambient Gamma Dose Rate

Abstract In the present study, variations in ambient gamma dose rate associated with snow cover were examined in a radioactive-contaminated site in Fukushima Prefecture, Japan. The ambient gamma dose rates decreased with increasing snow depth. The reduction trends were different between fresh snow (0.1–0.2 g/cm3) and granular snow (0.3–0.4 g/cm3) depending on snow density. Snow cover water content (snow water equivalent) calculated from snow depth and density was a key parameter governing the reduction in the ambient gamma dose rate. The ambient gamma dose rates reduced to 0.6 and 0.5 at 4 g/cm2 and 8 g/cm2 of snow water equivalent, respectively. Based on gamma-ray flux density distributions, the ambient gamma dose rates from the primary gamma rays decreased more compared to those from scattered gamma rays due to snow cover.

scholarly journals An Overview of Radiological Hazards Related to Geological External Gamma Radiation in Outdoor Environments

Proceedings ◽  
2018 ◽  
Vol 2 (10) ◽  
pp. 562
Author(s):  
Carlos Alves ◽  
Jorge Sanjurjo-Sánchez
Keyword(s):  
Gamma Radiation ◽  
Effective Dose ◽  
Dose Rate ◽  
Gamma Rays ◽  
Absorbed Dose ◽  
Absorbed Dose Rate ◽  
Radiological Hazards ◽  
Gamma Index ◽  
Outdoor Environments ◽  
Yearly Effective Dose

Rocks and soils are an important source of external gamma radiation due to their content in U, Th, and K. The dose rate derived from the emission of gamma-rays of radioisotopes can be directly measured or assessed from their content. In the present study, values of outdoor gamma radiation absorbed dose rate are analyzed to explore the implications of levels related to those values in terms of the exposure time necessary for attaining a certain yearly effective dose. We propose simple relations with the absorbed dose rate and with the gamma index of materials.

scholarly journals Evaluation of the gamma dose rate inside Egyptian buildings, utilizing theoretical and experimental techniques

2019 ◽  
Vol 34 (2) ◽  
pp. 175-180
Author(s):  
Elsayed Salama ◽  
Hala Soliman
Keyword(s):  
Monte Carlo Simulation ◽  
Dose Rate ◽  
Building Materials ◽  
Low Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Theoretical Methods ◽  
Thermoluminescent Dosimeter ◽  
Dose Rates ◽  
Room Model

The indoor low gamma dose rate exposures due to Egyptian room building materials are assessed by means of three different techniques: experimentally by using a thermoluminescent dosimeter, theoretically by using the general room model and by the Monte Carlo simulation through the RESRAD-BUILD software. The present study aims at validating the theoretical methods so that it can be amply used for measuring the low dose rates usually associated with the building materials. The measured in door dose rates were in the range of 55.92 ? 14.47 to 86.89 ? 16.68 nGyh?1 de pending on the position inside the room as obtained by the thermoluminescent dosimeter after 5 months' accumulation. Lower dose rates are obtained near the door and windows while higher dose rates are obtained at the center of the room, and close to the extended walls. Comparable results of the dose rates at same positions inside the room are obtained by the RESRAD-BUILD software. The room model is restricted to the room center and also gives comparable results. The three methods showed comparable results, which in turn confirm the recommendation of using theoretical ones, with RESRAD-BUILD software being more accurate.

Comparative study on the evaluation of gamma-dose rate above uranium mineralisation areas in Western Sudan

2003 ◽  
Vol 91 (7) ◽  
Author(s):  
A. K. Sam ◽  
D. A. Sirelkhatim
Keyword(s):  
Comparative Study ◽  
Dose Rate ◽  
Absorbed Dose ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
External Irradiation ◽  
Absorbed Dose Rate ◽  
Activity Concentrations ◽  
Uranium Mineralisation ◽  
Measured Activity

SummaryAbsorbed dose rate received from natural external irradiation in uranium mineralisation areas at Jebel Uro, Jebel Kurun and Jebel Mun was evaluated from the measured activity concentrations of

Assessment of natural radioactivity levels and the associated radiological hazards in some building materials from Mayo-Kebbi region, Chad

2018 ◽  
Vol 53 (4) ◽  
pp. 265-278 ◽  
Author(s):  
S. Penabei ◽  
D. Bongue ◽  
P. Maleka ◽  
T. Dlamini ◽  
Saïdou ◽  
...  
Keyword(s):  
Dose Rate ◽  
Natural Radioactivity ◽  
Building Materials ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Radiation Hazard ◽  
Absorbed Dose Rate ◽  
Activity Concentrations ◽  
Radiological Hazards ◽  
Radiation Hazard Index

In order to assess the levels of natural radioactivity and the associated radiological hazards in some building materials of the Mayo-Kebbi region (Chad), a total of nineteen samples were collected on the field. Using a high resolution γ-ray spectrometry system, the activity concentrations of radium (226Ra), thorium (232Th) and potassium (40K) in these samples have been determined. The measured average activity concentrations range from 0.56 ± 0.37 Bq kg−1 to 435 ± 7 Bq kg−1, 1.3 ± 0.6 Bq kg−1 to 50.6 ± 1.1 Bq kg−1 and 4.3 ± 2.0 Bq kg−1 to 840 ± 9 Bq kg−1, for 226Ra, 232Th and 40K, respectively. The highest 226Ra average activities is found in soil brick samples of Zabili. The highest mean value of 232Th and 40K concentrations are found in soil brick samples of Madajang. The activity concentration and the radium equivalent activity (Raeq) have been compared to other studies done elsewhere in the world. Their average values are lower than most of those of countries with which the comparison has been made. Were also evaluated, the external radiation hazard index, the internal radiation hazard index, the indoor air absorbed dose rate, the outdoor air absorbed dose rate, the activity utilization index, the annual effective dose, the annual gonadal dose equivalent, the representative level index, as well as, the excess lifetime cancer risk. In accordance with the criterion of the Organization for Economic Cooperation and Development, our results show that soil brick samples of Zabili and Madajang increases the risk of radiation exposure, thereby the possibility of developing cancer by people living in this environment. Based on these findings, brick samples from Zabili and Madajang are not recommended for construction purposes. All other sample materials have properties that are acceptable for use as building materials in terms of radiation hazard.

DETERMINATION OF RADON AND NATURAL RADIOACTIVITY CONCENTRATION IN SOME BUILDING MATERIALS USED IN IZMIR, TURKEY

2020 ◽  
Vol 15 (1) ◽  
pp. 107-118
Author(s):  
Daniel Hatungimana ◽  
Caner Taşköprü ◽  
Mutlu İçhedef ◽  
Müslim Murat Saç ◽  
Şemsi Yazıcı ◽  
...  
Keyword(s):  
Natural Radioactivity ◽  
Building Materials ◽  
Gamma Spectroscopy ◽  
Hazard Index ◽  
Absorbed Dose ◽  
Radiation Hazard ◽  
Absorbed Dose Rate ◽  
Dose Rates ◽  
Activity Concentrations ◽  
Materials Used

ABSTRACT The aim of this study is to determine the radon and natural radioactivity concentrations of some building materials and to assess the radiation hazard associated with those mortar materials when they are used in the construction of dwellings. Radon measurements were realized by using LR-115 Type 2 solid state nuclear track detectors. Radon activity concentrations of these materials were found to vary between 130.00 ± 11.40 and 1604.06 ± 40.5 Bq m−3. The natural radioactivity in selected mortar materials was analyzed by using scintillation gamma spectroscopy. The activity concentrations for 226Ra, 232Th and 40K for the studied mortar materials ranged from ND to 48.5 ± 7.0 Bq kg−1, ND to 41.0 ± 6.4 Bq kg−1 and ND to 720.4 ± 26.8 Bq kg−1, respectively. Radium equivalent activities, external and internal hazard indexes, gamma and alpha indexes and absorbed gamma dose rates were calculated to assess the radiation hazard of the natural radioactivity in studied samples. The calculated Raeq values of all samples were found to be lower than the limit of 370 Bq kg−1 set for building materials. The estimated hazard index values were found to be under the unity and the absorbed dose rate values were also below the worldwide average of 84 nGy h−1.

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