Organ DOSE and EFFECTIVE DOSE were estimated for one hundred patients (50 males and 50 females) who were reffered to Mashhad Ghaem Hospital for chest X-ray examination.ODS-60 software was employed for organ DOSE calculation. This software is capable of computing absorbed DOSE of 26 organs as well as EFFECTIVE DOSE. This programme is based on the ICRP-60 recommendation and Monte Carlo technique. Our results show that in PA chest X-ray lung absorbs the highest DOSE. The average value for males and females equals to 1.01± 0.14 and 0.58±0.10 mGy respectively. The resulting EFFECTIVE DOSE for men and women are equal to 0.246 ±0.034 and 0.178±0.033 mSv accordingly.EFFECTIVE DOSEs obtained from this research were compared with the results of other workers, also with NRPB national reference DOSE levels. It is concluded that EFFECTIVE DOSE as computed in this work is several times higher than similar quantities published by other workers. It implies that X-ray diagnostic procedures in Mashhad Ghaem Hospital should be re-examined and all efforts have to be made to reduce patient DOSE.

Background: Radon is one of the most common radioactive substances in underground mines which can enter the lungs and cause diseases. The purpose of this research is to measure the concentration of radon and the ANNUAL DOSE absorbed by miners at Sabz, Moslem, and Kamari caves in Neyshabur turquoise mine. The results are compared with standard permissible limits and can play a significant role in preventing risk of diseases in mone workers. Materials and Methods: The concentration of radon in the Neyshabur turquoise mine was measured at the depth of 250 m from the earth surface using the RTM1688 device. The obtained values were used to caculate the ANNUAL EFFECTIVE DOSE of radon absorbed by miners. Results: The results show that the concentration of radon was 5039. 33, 678. 46, and 3277 Bq. m-3 respectively at three locations of Sabz, Moslem, and Kamari caves with mean ANNUAL EFFECTIVE DOSEs in miners as 41. 07, 38. 78 and 26. 70 mSv per year, respectively. Conclusion: The measured concentration values are higher than the maximum permissible limit in three locations of the Neyshabur turquoise mine, and the mean ANNUAL EFFECTIVE DOSE was higher than the permissible limit in Sabz and Moslem caves. In order to prevent morbidity, it is suggested that working time be reduced, miners’ unnecessary traffic be avoided in high-DOSE locations, and high-efficiency ventilation be used.

Backgrounds and Objectives: Due to importance of ionizing radiation on human health, many studies have been performed to measure the background gamma radiation all around the world as well as some cities in lran. According to this fact that everybody spends almost 80% of his time in indoor areas, this study was carried out to measure the amount of background gamma radiation in indoor areas in Zanjan city located in northwest of Iran to determine the ANNUAL EFFECTIVE DOSE of the city residents.Materials and Methods: To determine the DOSE rate of background gamma radiation in indoors, 30 dwelling (in the main geographical directions and in the downtown areas) were selected. All of them were one floor and iron roofed. A Geiger-Muller detector (RDS-110) calibrated by Cs-137 was used in each livings room of each dwellings that performed in one meter far from the earth. In 30 minute 30 values was recorded. The mean value was considered as indoor gamma DOSE rate in each dwelling.Results: The mean value of DOSE rate in Zanajn indoor areas due to gamma background radiation was determined 146±25 nGy/h. According to the results and findings in our previous study about gamma background radiation in outdoor areas in Zanjan, the ANNUAL EFFECTIVE DOSE was determined and 0.87 mSv for Zanjan city residents.Conclusion: The ANNUAL EFFECTIVE DOSE of Zanjan city residents due to the gamma background radiation is 0.87 mSv that in comparison with UNSCEAR-2000 report is higher than the mean value for the world (0.48 mSv).

BACKGROUND AND OBJECTIVE: Nuclear medicine is one of the most important diagnostic modalities. The aim of present study was to estimate ANNUAL per capita EFFECTIVE DOSE in most common procedures performed in nuclear medicine centers in Iran in order to provide data for risk estimation due to exposure to ionizing radiation in nuclear medicine.METHODS: Corresponding data of patients underwent 5 main kinds of nuclear medicine exams in 10 major hospitals in Iran in six year period were used to estimate EFFECTIVE DOSE and also population DOSE due to exposure to ionizing radiation in nuclear medicine.FINDINGS: Based on the data of this study, the mean EFFECTIVE population DOSE per caput was 7.53 micro Sv per year.CONCLUSION: The mean EFFECTIVE population DOSE per caput per year is smaller than other countries and generally is similar to average background radiation in the world.

Purpose: Humans are always exposed to ionizing radiation from their environment, which can have destructive effects. This study aimed to measure background gamma radiation and estimate ANNUAL EFFECTIVE DOSE and excess cancer risk in Gonabad city. Materials and Methods: The DOSE rate due to indoor and outdoor background radiation was measured by RDS30 radiation survey meter at five zones on the map, including North, South, East, West, and center. Then, the ANNUAL EFFECTIVE DOSE and excess lifetime cancer risk were calculated by associated equations. Results: Mean DOSE rates for outdoor and indoor spaces were 0. 111 µ Sv/h and 0. 139 µ Sv/h, respectively. The mean background DOSE rate of indoor space was significantly higher than that of outdoor space. ANNUAL EFFECTIVE DOSE and excess lifetime cancer risk were obtained as 0. 817 and 2. 85×10-3, respectively. Conclusion: Background radiation DOSE, ANNUAL EFFECTIVE DOSE, and cancer risk for Gonabad city were higher than global ones. Further investigations are needed to encompass internal background radiation DOSEs in ANNUAL EFFECTIVE DOSE.

Background: Tea is one of the most popular beverages all over the world which is prepared from the leaves of a shrub camellia sinensis. Eastern Black Sea Region of Turkey which account for around 100% of all tea production in Turkey was among the areas contaminated by Chernobyl accident.Materials and Methods: A comprehensive study was planned and carried out to determine the level of gross α and b radioactivity and ANNUAL EFFECTIVE DOSE equivalent in different Turkish market tea using LSC.Results: The average measurements for digestion and infusion are 5.0 mBql-1 and 1.8 mBql-1 for gross a, 80.7 mBql-1 and 9.0 mBql-1 for gross b in tea samples. Contributions of the infusion tea samples to total ANNUAL EFFECTIVE DOSE equivalent from 238U, 234U, 230Th, 226Ra, 210Po, 232Th, 238Th, 210Pb and 228Ra are 0.103, 0.112, 0.480, 0.640, 2.742, 0.525, 0.164, 7.740 and 7.740 mSvy-1 for adults.Conclusion: The obtained results showed that natural activity concentrations of a- and b-emitting radionuclides and ANNUAL EFFECTIVE DOSE equivalent in tea samples did not exceed WHO recommended levels.

Background and purpose: Background radiation exists naturally in the environment and human has been always exposed to it. These rays can affect living creatures and cause chromosomal damage, and genetic and somatic diseases. Hot water springs are a major source of background radiation. This study aimed at investigating the absorbed DOSE of environmental gamma and determining the ANNUAL EFFECTIVE DOSE of hot water springs in South Khorasan province, Iran, during summer and autumn of 2018. Materials and methods: In order to measure the peripheral gamma of hot springs, the X5C PLUS dosimeter was used. Dosimetry was performed for all outdoor and indoor hot springs in two seasons (summer and autumn). The data for gamma irradiation were calculated and reported as nanosievert per hour and ANNUAL EFFECTIVE DOSE in milli-sievert per year. Data analysis was done in Excel and SPSS applying ANOVA. Results: In current study, the highest and lowest mean gamma radiation were found in Dig Rostam and Tabas hot springs, respectively. The mean EFFECTIVE DOSE in all outdoor hot springs was significantly lower than that in indoor hot springs (P <0. 001). Conclusion: The average gamma background radiation and the ANNUAL EFFECTIVE DOSE was lower than international standards in all outdoor hot springs, but in Ferdos and Sarbisheh hot springs (indoor) the mean values were higher than the standards which could be a threat for their customers and staff.

Background: The increasing health effects of nuclear radiation occasioned by enhanced human activities in the environment necessitated the need for constant evaluation and assessment of radiological impact on the general populace within a confined developmental area. Hence, Ten (10) drilled well water samples were collected from various cities distributed across Ondo and Ekiti states and analyzed for gamma-emitting radiations. Materials and Methods: The collected water samples were analyzed using n-type co-axial HPGe detector (Canberra Inc, USA), to determine the activity concentrations of the gamma emitting radiations, which was used with DOSE conversion factors to calculate the age dependent total ANNUAL EFFECTIVE DOSE equivalents to six different age groups and the committed EFFECTIVE DOSE for the age group >17y. Results: Activity concentrations ranged from 2. 25± 0. 39 to 35. 61± 6. 22 Bq l-1232Th, 7. 08± 1. 71 to 56. 68± 12. 50 Bq l-1226Ra, 45. 42± 2. 98 to 467. 61± 31. 69 Bq l-140K and 1. 66± 0. 46 to 25. 55± 5. 76 Bq l-1232Th, 4. 90± 1. 08 to 54. 18± 13. 34 Bq l-1226Ra, 41. 50± 2. 89 to 558. 82± 31. 69 Bq l-140K, respectively for Ondo and Ekiti States. Furthermore, the mean total ANNUAL EFFECTIVE DOSE equivalent for the age groups was found to be within the range of (2. 81 ± 0. 46 – 26. 91 ± 5. 11) mSv/y and (4. 71 ± 0. 92 – 23. 58 ± 5. 12) mSv/y respectively for Ondo and Ekiti states. Conclusion: This is above the 1. 0 mSv y-1 and 0. 1mSv y-1 respectively set by ICRP and WHO. Hence, the drilled wells are recommended for water screening to remove radionuclides.

Background: Man-made radionuclides, which are present in environment, have been created by human activities and added to the inventory of natural radionuclides for example 3H, 131I, 129I, 137Cs, 90Sr and 239Pu, in spite of the amount added is little compared to natural quantities. The aim of this study is to estimate the levels of radiological DOSEs in the soil samples collected from different locations in Kerbala city, Iraq. Materials and Methods: Thirty soil samples were collected from different sites of Karbala city and gamma-ray spectroscopy system with NaI (Tl) "1. 5×2" detector in low-background and 24 hours used to achieve the results. Results: The average values of absorbed gamma-ray DOSE rate, ANNUAL EFFECTIVE DOSE equivalent and ANNUAL gonadal DOSE equivalent were found to be 14. 09± 0. 32, 19. 59± 0. 39 and 112. 81± 2. 25 respectively. The average values of gamma representative level index and external hazard index resulting from natural radionuclides for all samples in the study area were 0. 25± 0. 005 and 0. 09± 0. 002 respectively. Conclusion: The obtained results in current work were compared with some results of soil samples in literature over the world. They do not exceed the upper limit calculated by UNSCEAR reports.