Abstract
Background:
The health implication of exposure to gamma radiation in the outdoor and indoor environments has become a major concern worldwide.Methods:
This study was conducted in the city of Birjand where three stations and buildings were randomly selected to measure the background radiation in outdoor and indoor places; for this purpose, GM detector (X5C plus) was used. All dose rates on the display of the survey meter were recorded, and the mean of all data in each station and buildings was computed and taken as the measured dose rate of that particular station.Results:
The average dose rate of background radiation was 71.8 nSv/h for outdoor and 82.0 nSv/h for indoor environments, and the maximum and minimum dose rates were 79.6 nSv/h and 61.7 nSv/h for outdoor measurements and 112.9 nSv/h and 70.8 nSv/h for indoor measurements, respectively.Conclusions:
The results revealed that the annual effective dose is 0.49 mSv, which is similar to that of the global level (0.48 mSv). The estimated excess lifetime cancer risk was 1.715 × 10-3, which was high compared to the world average value of 0.25 × 10-3.Keywords
Gamma Radiation Indoor and Outdoor Environment Dose Rate Annual Effective Dose and Excess Lifetime Cancer Risk
1. Background
We are continuously exposed to ionizing radiation. Background radiation emanates from primordial, cosmogenic and anthropogenic sources. Primaries are present in the earth's crust and exist all over the environment, including the human body itself (1). Cosmogenic radionuclides are born when cosmic radiations that are highly energetic and come from the sun and galactic radiation strike to the atmosphere, producing secondary radiation and uncharged particles such as protons, neutrons, pions and low-Z nuclei. In turn, the secondary particles produce cascade particles in the atmosphere (1-3). Human body irradiation from the external sources is largely due to radionuclides in uranium and thorium series and potassium-40 and their decay products that emit gamma radiation (1, 4). These radionuclides make up the earth and our building materials, which are common in rocks and soils, water, plants and air (4, 5). The radioactive radon gas is one of the decay products of these series. Background radiation causes nearly 80% of annual total radiation dose that a person is exposed to, which is 2.4 mSv per person. About 54% of the total external dose originates from K-40, Ra-226 and Ra-228 received by the public (6, 7). One of the main determinants of the background radiation is soil radioactivity concentration (8). Terrestrial radiation variation is typically larger than that of cosmic radiation (4).
The produced particles interact with the deoxyribonucleic acid (DNA) or produce free radicals. These free radicals travel to the DNA and lead to a change and breakage of chemical bonds, causing biological effects (3).
Anthropogenic sources produced from human activities, coming from the nuclear weapons testing in the atmosphere are the main man-made contribution to the environmental exposure of the world’s population (9). The ubiquitous form of irradiation is background radiation, so estimating the health risk of gamma radiation is highly important in health physics (10).
The mean annual global effective dose due to natural radiation sources has determined to be 2.4 mSv by the United Nations scientific committee on the effects of atomic radiation (UNSCEAR). A place is exposed to high levels of natural radiation (HLNR) if its natural radiation dose rate rises up to 10 mSv y-1. Therefore, environmental gamma radiation has been measured in many areas of the world, and the map of natural radiation of these areas has been plotted (11).
2. Objectives
The aim of this study was to present the background indoor and outdoor radiation dose rates and estimate the annual effective dose and excess cancer risk to the residents of Birjand.
3. Methods
The study area was the city of Birjand, located in the Eastern part of Iran, with a total population of 240,894 (32°52’N 59°12’E) as shown in Figure 1. For measurement purposes, the map of the sites was divided into five segments as North, East, South, West and center. To measure the outdoor and indoor background radiation, three stations and buildings were randomly selected. For each measurement, the device was placed on an aluminum holder at one meter above the ground level for half an hour to avoid the effects of the ground and buildings on the outdoor and from the walls to satisfy the criteria of the indoor environment. Preferentially, the ground level was grassy. Readings were obtained in the middle of the day. Background dose equilibrium measurements rate was done in the first six- month of 2016, and background dose rate was read every minute in each station.
Partial Map of the Indoor and Outdoor Background Radiation (Google Map)
For measurement purposes, similar and common masonry buildings were selected, and GM detector (X5C plus), calibrated by the manufacturer for a period of two years, was used. All dose rates on the display of the survey meter were recorded, and the mean of all data in each station and buildings was computed and taken as the measured dose rate of that particular station. The annual effective dose of background radiation was estimated as follows (12):
Where E (nSv) is annual effective dose, Dout and Din (nSv/h) are mean outdoor and indoor absorbed dose rates, T (hour) is time to convert from year to hour (24 hours × 365.25), OFout and OFin are outdoor and indoor occupancy factors (20% and 80% for outdoor and indoor, respectively) and f is conversion coefficient (0.7 for adults) reported by The United Nation scientific committee on the effect of atomic radiation (UNSCEAR) to convert absorbed dose in the air to the effective dose (13).
It is necessary to measure the excess lifetime cancer risk due to gamma radiation (14). Based on the annual effective dose, excess lifetime cancer risk was calculated as follows (8):
Where E is the annual effective dose, DL is duration of life (70 years), and RF is the risk factor (Sv-1) or fetal cancer risk per sievert. The value of 0.05 for the public exposure was used by the ICRP (international commission on radiological protection) for stochastic effects (15).
4. Results
The mean dose rates of outdoor and indoor background radiation, the corresponding effective dose rates and excess lifetime cancer risk in five parts of Birjand are summarized and presented in Table 1. Based on the results, the average dose rate of background radiation was 71.8 nSv/h for outdoor and 82.0 nSv/h for indoor environments, and the maximum and minimum dose rates were 79.6 nSv/h and 61.7 nSv/h for outdoor measurements, and 112.9 nSv/h and 70.8 nSv/h for indoor measurements, respectively.
Using Equation 1 and the dose rates of background radiation (indoor and outdoor), the estimated annual effective dose of adults in birjand was calculated as follows:
E = (71.8 × 0.2 + 82.0 × 0.8) × 8766 × 0.7 = 0.49 mSv/y
Using Equation 2, excess lifetime cancer risk was calculated as follows:
Excess lifetime cancer risk = 0.49 × 70 × 0.05 = 1.72×10-3
The Average Outdoor and Indoor Background Dose Rates, Achieved Effective Dose, and Excess Lifetime Cancer Risk in the Selected Parts of Birjand
| Segment | Average Indoor Dose Rate (nSv/h) | Range | Average Outdoor Dose Rate (nSv/h) | Range | Effective Dose Rate (mSv/y) | Excess Lifetime Cancer Risk (×10-3) |
|---|---|---|---|---|---|---|
| North | 70.77 | 46 - 114 | 75.81 | 31 - 140 | 0.44 | 1.54 |
| South | 75.15 | 31 - 154 | 62.47 | 31 - 95 | 0.45 | 1.58 |
| East | 79.70 | 30 - 277 | 79.60 | 38 - 138 | 0.49 | 1.72 |
| Center | 112.88 | 47 - 280 | 65.55 | 30 - 138 | 0.63 | 2.21 |
| West | 79.00 | 30 - 143 | 61.77 | 31 - 97 | 0.46 | 1.61 |
5. Discussion
GM detector (X5C plus) was used to obtain the results of this study. The results obtained by this detector revealed that the mean outdoor and indoor dose rates in the selected areas were about 71.8 and 82.0 nSv/h, respectively. These values were mainly because of the materials of the construction in indoor exposure and from terrestrial radionuclides that existed at trace levels in the soil and because of cosmic rays in outdoor exposure (12). In some cases, the outdoor data in this study was lower than the mean values from the other cities in Iran such as Isfahan (137 nSv/h), Lorestan province (113 nSv/h), Gilan province (94 nSv/h), and Oromeih (154 nSv/h). Moreover, in some cases, it was higher than that of the other cities in Iran such as Bushehr (51.8 nSv/h), Chabok sar (71 nSv/h), Kela Chay (65 nSv/h), and Pareh Sar (67 nSv/h) (10, 11, 16). The lowest values in the world are in Cyprus, Iceland, Egypt, the Netherlands and the United Kingdom, all of which the values were less than 40 nSv/h. However, Australia, Malaysia, and Portugal had the highest values, greater than 80 nSv/h. The lowest indoor values were found in New Zealand, Iceland and the United States, which were below 40 nSv/h, and the highest values were found in Hungary, Malaysia, China, Albania, Portugal, Australia, Italy, Spain, Sweden, and Iran (greater than 95 nSv/h), which might be due to the extensive use of stone or masonry materials in buildings (12). The results revealed that the effective dose due to background radiation in Birjand was similar to that of the global level. As reported by the UNSCEAR, environmental gamma radiation average for adults is 0.48 mSv worldwide, and the individual country results were within the 0.3 - 0.6 mSv range. The values are about 10% and 30% higher for children and infants (12).
The excess lifetime cancer risk which is 1.715 × 10-3 is high as compared to the world average value of 0.25 × 10-3 (12). This is due to terrestrial nuclear radiation.
5.1. Conclusion
To evaluate the health hazards, it is important to determine background radiation level. The indoor and outdoor dose rates, and the annual effective dose and excess lifetime cancer risk to the residents were measured. The average dose rates of background radiation were 71.8 nSv/h for outdoor and 82.0 nSv/h for indoor environments. The annual effective dose was 0.49 mSv, and the estimated excess lifetime cancer risk was 1.715×10-3. The results were similar compared to global levels.
Acknowledgements
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