OTHERS_CITABLE Dose distribution evaluation of various dose calculation algorithms in inhomogeneous media Background: Dose calculation algorithms play a very important role in predicting the explicit dose distribution. We evaluated the percent depth dose (PDD), lateral depth dose profile, and surface dose volume histogram in inhomogeneous media using calculation algorithms and inhomogeneity correction methods. Materials and Methods: The homogeneous and inhomogeneous virtual slab phantoms used in this study were manufactured in the radiation treatment planning system to represent the air, lung, and bone density with planned radiation treatment of 6 MV photons, a field size of 10 × 10 cm2, and a source-to-surface distance of 100 cm. Results: The PDD of air density slab for the Acuros XB (AXB) algorithm was differed by an average of 20% in comparison with other algorithms. Rebuild up occurred in the region below the air density slab (10–10.6 cm) for the AXB algorithm. The lateral dose profiles for the air density slab showed relatively large differences (over 30%) in the field. There were large differences (20.0%–26.1%) at the second homogeneous–inhomogeneous junction (depth of 10 cm) in the field for all calculation methods. The surface dose volume histogram for the pencil beam algorithm showed a response that was approximately 4% lower than that for the AXB algorithm. Conclusion: The dose calculation uncertainties were shown to change at the interface between different densities and in varied densities using the dose calculation methods. In particular, the AXB algorithm showed large differences in and out of the field in inhomogeneous media. http://ijrr.com/article-1-1811-en.pdf 2016-12-18 269 278 10.18869/acadpub.ijrr.14.4.269 Keywords: Inhomogeneous media calculation algorithms correction methods PDD dose profiles. Y.L. Kim 1 Department of Radiology, Choonhae College of Health Science, Ulsan 689-784, South Korea AUTHOR T.S. Suh 2 Department of Radiology, Choonhae College of Health Science, Ulsan 689-784, South Korea AUTHOR B.Y. Choe 3 Department of Radiology, Choonhae College of Health Science, Ulsan 689-784, South Korea AUTHOR B.O. Choi 4 Department of Radiation Oncology, Seoul St. Mary’s Hospital, The Catholic University, Seoul 137-701, South Korea AUTHOR J.B. Chung 5 Department of Radiadion Oncology, Seoul National University Bundang Hospital, Seongnam 463-707, South Korea AUTHOR J.W. Lee 6 Department of Radiation Oncology, Konkuk University Medical Center, Seoul 143-729, South Korea AUTHOR Y.K. Bae 7 Department of Radiation Oncology, Konkuk University Medical Center, Seoul 143-729, South Korea AUTHOR B.M. Park 8 Department of Radiation Oncology, Konkuk University Medical Center, Seoul 143-729, South Korea AUTHOR J.Y. Jung 9 Department of Radiation Oncology, Inje University Sanggye Paik Hospital, Seoul 139-707, South Korea AUTHOR Y.J. Shin 10 Department of Radiation Oncology, Inje University Sanggye Paik Hospital, Seoul 139-707, South Korea AUTHOR
OTHERS_CITABLE Optimal timing of computed tomography for assessing lymph nodes after neoadjuvant chemoradiotherapy for rectal cancer Background: This study assessed the optimal timing of computed tomography for detection of metastatic disease in locoregional lymph nodes in patients with rectal cancer who have undergone chemoradiotherapy. Materials and Methods: This observational retrospective study was performed in a single institution. All patients with locally advanced rectal cancer treated with chemoradiotherapy, followed by a total mesorectum excision from January 1, 2003 to December 31, 2012, were included. Lymph node metastases evident on preoperative computed tomography were compared with postoperative pathologic lymph node status. Results: The study population consisted of 108 patients: Group A (nodal negative on preoperative computed tomography, n = 52) and Group B (nodal positive on preoperative computed tomography, n = 56). Analysis of the computed tomography scans in Group A revealed a high ability (98.07%) to predict negative lymph nodes, compared to 58.92% for predicting positive lymph nodes in Group B. Conclusion: The results of this study suggest that the optimal timing of computed tomography for assessing lymph nodes after neoadjuvant chemoradiotherapy for rectal cancer is after 6 weeks; this timing might be key for prediction of complete clinical responses.   http://ijrr.com/article-1-1812-en.pdf 2016-12-18 279 285 10.18869/acadpub.ijrr.14.4.279 Keywords: Computed tomography chemoradiotherapy rectum cancer complete clinical response. C.L. Lai 1 Division of Colon and Rectal Surgery, Department of Surgery, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR M.J. Lai 2 Division of Clinical Pathology, Department of Pathology, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR C.H. Liu 3 Department of Radiology, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR C.C. Wu 4 Division of Colon and Rectal Surgery, Department of Surgery, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR S.W. Jao 5 Division of Colon and Rectal Surgery, Department of Surgery, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR C.W. Hsiao 6 Division of Colon and Rectal Surgery, Department of Surgery, Tri-Service General Hospital, National Defense Medical Center, Taipei, Taiwan, Republic of China AUTHOR
OTHERS_CITABLE Use of a 3D printer to create a bolus for patients undergoing tele-radiotherapy Background: This study describes the possibility of implementing three-dimensional printing technology to create a precise construction of a planned bolus, based on computed tomography information stored in the Digital Imaging and Communications in Medicine (DICOM) format file. Materials and Methods:  To create the bolus with a 3D printer, we converted data in the DICOM format to the stereolithography (STL) format. In addition, we produced a paraffin bolus that, traditionally, is manually placed directly on the patient. CT scans were acquired for both boluses, and the images were superimposed onto the patient CT scans that were used to design the bolus. The superimposition of images was performed to compare the fit of the bolus printed on a 3D printer to that of the paraffin bolus made in the traditional way. In addition, for both models, the dose distribution was simulated. To quantify the level of matching ML, special formula was used. The ML parameter had a value between 0 and 100%, where 100% indicated a perfect fit between the model and the 3D printed bolus. Results: We verified that 100% of the volume of the 3D printed bolus was located within the contour of the designed model. The ML of the bolus was 94%. For the classical paraffin bolus the ML was only 28%. Conclusion: A bolus printed on a three-dimensional printer can faithfully reproduce the structure specified in the project plan. Compared to the classical paraffin bolus, the three-dimensional printed bolus more closely matched the planned model and possessed greater material uniformity http://ijrr.com/article-1-1813-en.pdf 2016-12-18 287 295 10.18869/acadpub.ijrr.14.4.287 Keywords: Bolus material 3D printing teleradiotherapy DICOM format STL format. M. Lukowiak 1 Department of Medical Physics, West Pomeranian Oncology Center, Szczecin, Poland AUTHOR M. Boehlke 2 Department of Medical Physics, West Pomeranian Oncology Center, Szczecin, Poland AUTHOR M. Lewocki 3 Department of Medical Physics, West Pomeranian Oncology Center, Szczecin, Poland AUTHOR W. Kot 4 Department of Medical Physics, West Pomeranian Oncology Center, Szczecin, Poland AUTHOR D. Matias 5 Copernicus Sp. zo.o., Szczecin, Poland AUTHOR M. Piątek- Hnat 6 Institute of Polymers, Department of Biomaterials and Microbiological Technology, West Pomeranian University of Technology, Szczecin, Poland AUTHOR M. El Fray 7 Institute of Polymers, Department of Biomaterials and Microbiological Technology, West Pomeranian University of Technology, Szczecin, Poland AUTHOR K. Jezierska 8 Department of Medical Physics, Pomeranian Medical University, Szczecin, Poland AUTHOR W. Podraza 9 Department of Medical Physics, Pomeranian Medical University, Szczecin, Poland AUTHOR
OTHERS_CITABLE Prostate-specific antigen kinetics after hypofractionated stereotactic body radiotherapy for localized prostate cancer Background: stereotactic body radiotherapy (SBRT) has emerged as an effective treatment for localized prostate cancer. However, prostate-specific antigen (PSA) kinetics after SBRT has not been well characterized. The objective of the current study is to analyze the rate of PSA decline and PSA nadir following hypofractonated SBRT in localized prostate cancer. Materials and Methods: From 2008 to 2014, thirty-nine patients newly diagnosed, localized prostate (25.6% low risk, 66.7% intermediate risk and 7.7% high risk) cancer were treated with SBRT using Cyberknife. Total dose of 36.25 Gy in 5 fractions of 7.25 Gy were administered. No one received androgen deprivation therapy (ADT). PSA nadir and rate of change in PSA (slope) were calculated and compared. Results: With a median follow-up of 52 months (range, 13-71), the median rates of decline of PSA were -0.372, -0.211 and -0.128 ng/mL/month, respectively, for durations of 1, 2 and 3 years after radiotherapy, respectively. The decline of PSA was maximal in the first year and continuously decreased for durations of 2 and 3 year. The median PSA nadir was 0.28 ng/mL after a median 33 months. There was one biochemical failure, occurring in a high risk patient. 5-year actuarial biochemical failure (BCF) free survival was 94.2%. Conclusion: In this report of localized prostate cancer, continuous decrease of PSA level for duration 1, 2 and 3 year following SBRT using Cyberknife resulted in lower PSA nadir. Also, SBRT leaded to long-term favorable BCF-free survival. http://ijrr.com/article-1-1814-en.pdf 2016-12-18 297 303 10.18869/acadpub.ijrr.14.4.297 Keywords: Stereotactic body radiotherapy prostate cancer Cyberknife PSA kinetics PSA nadir. H.J. Kim 1 Department of Radiation Oncology, Inha University Hospital, Inha University of Medicine, Inchon, Korea AUTHOR J.H. Phak 2 Department of Radiation Oncology, Inha University Hospital, Inha University of Medicine, Inchon, Korea AUTHOR W.Ch. Kim 3 Department of Radiation Oncology, Inha University Hospital, Inha University of Medicine, Inchon, Korea AUTHOR
OTHERS_CITABLE Optimisation of the MAGAT gel dosimeter compositions Background: An effective polymer gel dosimeter can be fabricated by varying the composition of its chemical components. Materials and Methods: The MAGAT gel dosimeter formulations that used different compositions of Methacrylic acid (MAA) and gelatin were extensively investigated in the present study according to the R2–dose response and R2–dose sensitivity. The irradiation of MAGAT gel was performed by 6-MV photon beam at a dose range 1 to 10 Gy and was imaged by 1.5T Magnetic Resonance Imaging (MRI). The dose response of MAGAT gel dosimeter was obtained from spin-spin relaxation rate (R2) of MRI signal. Results: The MAGAT gel dosimeter composed of 5% gelatin and 6% MAA gave the highest sensitivity (1.1180            s-1Gy-1). Conclusion: Understanding the effects of the compositional changes will help to clarify the mechanisms involved in the dose response of the MAGAT gel dosimeter.   http://ijrr.com/article-1-1815-en.pdf 2016-12-18 305 311 10.18869/acadpub.ijrr.14.4.305 Keywords: MAGAT gel dosimeter spin-spin relaxation rate (R2) dose response MRI imaging. N.N.A Razak 1 School of Physics, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR A.A. Rahman 2 1School of Physics, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR S. Kandaiya 3 1School of Physics, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR I.S. Mustafa 4 1School of Physics, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR A.A. Mahmoud 5 1School of Physics, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR N.Z. Yahaya 6 School of Distance Education, University Sains Malaysia, 18000, Pulau Pinang, Malaysia AUTHOR
OTHERS_CITABLE Thorax organ dose estimation in computed tomography based on patient CT data using Monte Carlo simulation Background:  This study presents patient specific and organ dose estimation in computed tomography (CT) imaging of thorax directly from patient CT image using Monte Carlo simulation.  Patient's CT image is considered as the patient specific phantom and the best representative of patient physical index in order to calculate specific organ dose. Materials and Methods: EGSnrc /BEAMnrc Monte Carlo (MC) System was used for CT scanner simulation and DOSXYZnrc was used in order to produce patient specific phantom and irradiation of photons to phantom in step and shoot mode (axial mode). In order to calculate patient thorax organ dose, patient CT image of thorax as voxelized phantom was divided to a 64x64x20 matrix and 6.25 x 6.25 x 6.25 mm3 voxel size and this phantom was imported to DOSXYZnrc code. MC results in unit of Gy/particle were converted to absorbed dose in unit of mGy by a conversion factor (CF). We calculated patient thorax organ dose in MC simulation from all irradiated slices, in 120 kV and 80 kV photon energies. Results: Effective dose was obtained from organ dose and organ weighting factor. Esophagus and spinal cord received the lowest, and bone received the highest dose. In our study, effective dose in CT of thorax was 7.4 mSV and 1.8 mSv in 120 and 80 kV, respectively. Conclusion: The results of this study might be used to provide the actual patient organ dose in CT imaging and calculation of real effective dose based on organ dose. http://ijrr.com/article-1-1816-en.pdf 2016-12-18 313 321 10.18869/acadpub.ijrr.14.4.313 Keywords: Organ dose patient specific dose computed tomography MC simulation EGSnrc/BEAMnrc. Gh.R. Fallah Mohammadi1 1 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Ira AUTHOR N. Riyahi Alam 2 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Ira AUTHOR Gh. Geraily 3 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Ira AUTHOR R. Paydar 4 Radiation Sciences Department, Faculty of Allied Medicine, Iran University of Medical Sciences, Tehran, Iran AUTHOR
OTHERS_CITABLE External dose measurements in the Eloor industrial area in the Ernakulam district of Kerala, India Background: Natural background radiation of a particular region is one of the distinctive factors defining the status of environment. Eloor Island is an industrial area in Ernakulum District of the state of Kerala, India. The indoor and outdoor gamma level measurements have been carried out for the region for evaluating the annual effective dose to the population residing in this area. Materials and Methods:  Measurements of indoor gamma dose were done for a whole year using Thermo Luminescent Dosimeters (TLDs) and GM tube based survey meters in forty five selected locations. The activity concentration of 232Th, 238U and 40K in the samples were analyzed using gamma spectrometry. The outdoor external gamma ray dose rates were evaluated from the activity concentration of 40K, 238U and 232Th in the soil samples collected from the study area. Results: The average indoor gamma dose measured using TLDs were found to be 1219 µGy y-1.  The measured activity in the soil samples had range from 92.5 Bq kg-1 to 792.8 Bq kg-1 for 232Th, 9.2 Bq kg-1 to 114.6 Bq kg-1 for 238U and 265.9 Bq kg-1 to 851.9 Bq kg-1 for 40K. From the observed mean dose levels, the annual effective dose equivalent to population residing in the island has been estimated and is found to be 0.68 mSv y-1 for indoors and 0.32 mSv y-1 for outdoors. Conclusion: The annual effective dose equivalent to population estimated for indoor is found to be higher as compared to the global average the same for outdoor was found to be less when compared with the natural background gamma level reported by UNSCEAR for normal background areas http://ijrr.com/article-1-1817-en.pdf 2016-12-18 323 329 10.18869/acadpub.ijrr.14.4.323 Keywords: Eloor island indoor dose outdoor dose annual effective dose. D. Balakrishnan 1 Department of Physics, The Cochin College, Kochi-2, Kerala, India AUTHOR J.P. Abraham 2 Department of Physics, The Cochin College, Kochi-2, Kerala, India AUTHOR A.G. Umadevi 3 Department of Chemistry, NSS College, Ottapalam, Palakkad, Kerala, India AUTHOR A. Sunil 4 Department of Physics, Fatima Mata National College, Kollam, Kerala, India AUTHOR P.J. Jojo 5 Department of Physics, Fatima Mata National College, Kollam, Kerala, India AUTHOR S. Ben Byju 6 Department of Physics, Fatima Mata National College, Kollam, Kerala, India AUTHOR S. Radhakrishnan 7 Bhabha Atomic Research Centre, Health Physics Unit, IREL, Udyogmandal, Kerala, India AUTHOR M. Harikumar 8 Bhabha Atomic Research Centre, Health Physics Unit, IREL, Udyogmandal, Kerala, India AUTHOR
OTHERS_CITABLE Indoor radon measurements in residential dwellings in Qom, Iran Background: Inhalation of radon and its short-lived decay products is one of the ‎most significant sources of exposure to natural radiation. Radon is the second cause ‎of lung cancer in the populations. The present study was carried out under the projects of ‎national radon, with the aim of determining the concentration of indoor in the city of Qom ‎located in the central semi-arid region of Iran.‎ Materials and Methods: Radon measurements were carried out in 123 dwellings ‎using passive sampling with CR-39 detectors for 90 days. The map of radon ‎concentration distribution was prepared using Arc GIS software and the statistical ‎analysis was performed with SPSS version 20. Results: Indoor radon concentrations in Qom dwellings ranged from 15–259 Bq ‎m-‎‎3‎. The arithmetic mean of indoor radon concentrations on basement, ground floors, ‎first floors and second and upper floors were ‎123.43, 87.94, 63.72 and 40.69‎‏ ‏Bq m-3, ‎respectively. Conclusion: A correlation was found between the distances from fault zones and measured ‎indoor radon concentration. In most of cases, radon values were lower in well- ‎ventilated dwellings in comparison with poorly-ventilated ones. Moreover, high radon ‎concentration levels were observed in basements. The results indicated that in 30 ‎places (24.3% of cases), the radon concentrations were higher than the reference levels ‎recommended by the World Health Organization (100 Bq m-3). http://ijrr.com/article-1-1818-en.pdf 2016-12-18 331 339 10.18869/acadpub.ijrr.14.4.331 Keywords: Indoor radon CR-39 dwelling floor fault. M. Fahiminia 1 Research Center for Environmental Pollutants, Qom University of Medical Sciences, Qom, Iran AUTHOR R. Fouladi Fard 2 Research Center for Environmental Pollutants, Qom University of Medical Sciences, Qom, Iran AUTHOR R. Ardani 3 Research Center for Environmental Pollutants, Qom University of Medical Sciences, Qom, Iran AUTHOR A. Mohammadbeigi 4 Research Center for Environmental Pollutants, Qom University of Medical Sciences, Qom, Iran AUTHOR K. Naddafi 5 Department of Environmental Health Engineering, School of Public Health, Tehran University of Medical Sciences, Tehran, Iran AUTHOR M.S. Hassanvand 6 Center for Air Pollution Research (CAPR), Institute for Environmental Research (IER), Tehran University of Medical Sciences, Tehran, Iran AUTHOR
OTHERS_CITABLE Establishment of CT diagnostic reference levels in select procedures in South India Background: To suggest South India CT diagnostic reference levels (DRLs) by collecting radiation doses for the most commonly performed CT examinations. Materials and Methods: A pilot study investigated the most frequent CT examinations. 110 CT sites were asked to complete a survey booklet to allow the recording of CT parameters for each of 3 CT examinations during a 1 year time period. Dose data such Volumetric Computed Tomography Dose Index (CTDIv) and Dose length product (DLP) on a minimum of 50 average-sized patients in each category were recorded to calculate a mean site CTDIvol and DLP value. The rounded 75th percentile was used to calculate a DRL for each site and the region by compiling all results. Results are compared with international DRL data. Results: Data were collected for 16,500 patients. All equipment had multislice capability (2-256 slices). DRLs are proposed using CTDIvol (mGy) and DLP (mGy.cm) for CT head (47 and 1041 respectively), CT chest (10 and 445 respectively), and CT abdomen (12 and 550 respectively). These values are lower than current DRLs and comparable to other international studies. Wide variations in mean doses are noted across the region. Conclusion: Baseline figures for South India CT DRLs are provided on the most frequently performed CT examinations. It was noted that there was a wide variation in mean doses among the CT scanners used during diagnosis. The differences in CT doses between CT scanner departments as well as identical scanners suggest a large potential for optimization of examinations. http://ijrr.com/article-1-1819-en.pdf 2016-12-18 341 347 10.18869/acadpub.ijrr.14.4.341 Keywords: Computed tomography (CT) weighed computed tomography dose index (CTDIw) volumetric computed tomography dose index (CTDIv) dose length product (DLP) dose reference level (DRL). A. Saravanakumar 1 Department of Applied Science, PSG College of Technology, Coimbatore 641 004, India AUTHOR K. Vaideki 2 1Department of Applied Science, PSG College of Technology, Coimbatore 641 004, India AUTHOR K.N. Govindarajan 3 Department of Radiology, PSG Institute of Medical Science and Research & Hospitals, Coimbatore 641004, India AUTHOR B. Devanand 4 Department of Radiology, PSG Institute of Medical Science and Research & Hospitals, Coimbatore 641004, India AUTHOR S. Jayakumar 5 Department of Physics, PSG Institute of Technology and Applied Research, Coimbatore 641 062, India AUTHOR S.D. Sharma 6 Radiological Physics and advisory division, Bhabha Atomic Research Centre, Mumbai- 400094, India AUTHOR
OTHERS_CITABLE Basic investigation on performance of low-density polymer gel dosimeter Background:  In this study a series of basic dosimetric properties of a low-density (LD) gel dosimeter are investigated. The dose response is studied regarding to linearity, sensitivity, dose-rate and energy dependence as well as lung tissue equivalence. Materials and Methods: The LD gel was made by mixing the polymer gel with expanded polystyrene spheres. Energy dependence was studied at two different energies: 1.25 MeV and 6 MV photon beams which were produced by 60Co and Linac machines. Investigation of dose rate dependence was performed in the low, medium, and high absorbed dose regions. Also reproducibility of dose response was studied in three sets of LD gel with identical preparation, irradiation and imaging procedure at three different days. Moreover the linearity and sensitivity were investigated up to 30Gy. Results: The results showed that the dose response was reproducible. The gel response was found linear up to 22Gy with r2=0.981 and sensitivity of 0.814S-1Gy-1. In the measured ranges, the dose response of LD gel was independent of beam energy within less than ±0.02 and dose rate had no effect on the gel response. LD gel was nearly lung tissue equivalent with mass density 0.37 to 0.4g/cm3 and relative electron density 0.41. Conclusion: MAGAT LD gel dosimeter appears to be a promising dosimeter in all aspects of dosimetric properties evaluated in this study. In addition, its high linearity together with no dose rate dependence in different level of absorbed doses makes it a suitable dosimeter to measure 3D-dose distributions inside a non-homogeneous media. http://ijrr.com/article-1-1820-en.pdf 2016-12-18 349 353 10.18869/acadpub.ijrr.14.4.349 Keywords: Lung tissue dosimetry polymer gel dosimeter basic radiation properties MAGAT. F. Pake 1 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Iran AUTHOR A. Takavar 2 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Iran AUTHOR H.A. Nedaie 3 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Iran AUTHOR H.R. Saligheh Rad 4 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Iran AUTHOR E. Eqlimi 5 Department of Medical Physics and Biomedical Engineering, Faculty of Medicine, Tehran University of Medical Sciences, Tehran, Iran AUTHOR V. Vaezzadeh 6 Department of Radiotherapy Oncology, Cancer Research Centre, Cancer Institute, Tehran University of Medical Sciences, Tehran, Iran AUTHOR M. Shojaee Moghadam 7 Medical imaging center, Payambaran Hospital, Tehran, Iran AUTHOR
OTHERS_CITABLE Increased Mercury release due to exposure to electromagnetic radiation as a limiting factor for using dental amalgam Background: Although it is one of the most toxic nonradioactive elements, mercury is widely used in dental amalgam. Mercury is a toxic element which can damage various organs such as central nervous system, renal, respiratory and hematologic systems. The adverse health impacts associated to exposure to some common sources of electromagnetic fields including laptop computers, mobile phones, MRI and mobile phone jammers have been evaluated by our laboratory in our previous investigations. In this study, we aimed to evaluate the effect of X ray exposure on microleakage of amalgam restoration. Materials and Methods: Standardized class V cavities were prepared on the buccal surfaces of 46 non-carious freshly extracted human premolars. The teeth were randomly divided into experimental and control groups. Experimental group were exposed to X-ray using an intraoral radiography machine at 60 kVp, 0.1 s, 7 mA with 2.5 mm Al total filtration. The absorbed dose was 245.0 ± 0.5 µGy. All specimens were placed in 2 % basic fuchsin solution for 24 hours. Then the specimens were sectioned and microleakage was assessed according to dye penetration using a stereomicroscope. Statistical analysis was performed with the Mann-Whitney U-test. Results: Microleakage was significantly higher in the X-ray exposed teeth compared to those of the non-irradiated samples. Conclusion: The results of the present study suggest that X-ray exposure increased microleakage of amalgam restorations http://ijrr.com/article-1-1821-en.pdf 2016-12-18 355 359 10.18869/acadpub.ijrr.14.4.355 Keywords: X-ray radiography radiation amalgam microleakage mercury. M. Paknahad 1 Oral and Dental Disease Research Center, Department of Oral and Maxillofacial Radiology, School of Dentistry, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR A. Dehghani 2 Biomaterial Research Center, Department of Oral and Maxillofacial Pathology, School of Dentistry, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR S. Jarideh 3 Ionizing and Non-ionizing Radiation Protection Research Centre (INIRPRC), Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR M. Haghani 4 Ionizing and Non-ionizing Radiation Protection Research Centre (INIRPRC), Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR H. Mozdarani 5 Department of Medical Genetics , School of Medical Sciences, Tarbiat Modares University, Tehran, Iran AUTHOR G. Mortazavi 6 Dentist, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR J. Eslami 7 Anesthesiology Department, School of Nursing and Midwifery, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR S.M.J Mortazavi 8 Department of Medical Physics , School of Medicine, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR
OTHERS_CITABLE Measurement of radium-226 concentration and dose calculation of drinking water samples in Guilan province of Iran Background: Radium-226 (226Ra) is a product of the 238U radionuclide decay series that significantly incorporated into the human body through water intake. It can also potentially cause a series of health problems including cancers of the digestive system. Radium-226 (226Ra) is a product of the 238U radionuclide decay series that significantly incorporated into the human body through water intake. It can also potentially cause a series of health problems including cancers of the digestive system. Materials and Methods: 226Ra has been determined in drinking water samples collected from various locations of Guilan province of Iran. The water samples are taken from public water and urban tap water sources. For evolution of gross a and b exposure precipitation method and proportional scintillator system was used. The radon emanation method was used to measure the radium concentration in drinking water. Results: The measurements showed the gross α and β concentration ranges were between <38 mBql-1 to 92 mBql-1 and <41 mBql-1 to 328 mBql-1, respectively. The radium concentration range was between 2 mBq l-1 to 38.2 mBq l-1. The resulting contribution to the annual effective dose due to the digestion of 226R in water was calculated to be between <0.4 μSv y-1 to 7.8 μSv y-1, respectively. Conclusion: The average concentration of 226Ra was found (7.6 mBq l-1) in drinking water samples and the average annual effective dose, from the digestion of 226Ra in water samples was calculated to be 1.5 µSv y-1. According to UNSCEAR, the annual effective dose value by ingestion is report to be 0.12 mSv y-1. http://ijrr.com/article-1-1822-en.pdf 2016-12-18 361 366 10.18869/acadpub.ijrr.14.4.361 Keywords: Radium-226 ingestion drinking water precipitation method. A. Abbasi 1 Nuclear Science and Technology Institute, (NSTI), Tehran, Iran AUTHOR V. Bashiry 2 Faculty of Engineering, Cyprus International University, Nicosia, Northern Cyprus, Mersin 10, Turkey AUTHOR
OTHERS_CITABLE Assessment of radon gas using passive dosimeter in Amman and Al-Rusaifa cities, Jordan Background: Radon concentration was measured in the soil and indoor of Amman and Al- Rusaifa cities in Jordan during summer season. Materials and Methods: The measurement was performed using time-integrated passive radon dosimeters, containing a solid state nuclear track plastic detector, commercially known as CR-39. Results: Radon concentration levels in the soil ranged from 2.8 ± 1.2 to 6.9 ± 1.5 (kBq/m3) with an average  4.0 ± 1.6 (kBq/m3)  in Amman and  from and  6.5± 1.1 to  22.4 ± 5.2 kBq/m3  in Al- Rusaifa  with average 14.2 ± 2.5 (kBq/m3). The average indoor radon concentration in the first floor in Amman was 44.8± 5.3 (Bq/m3); while the average concentration in Al- Rusaifa, in the first floor, was 187± 16.35 (Bq/m3). In Al- Rusaifa, our results in the ground floor and the first floor were about 11% - 26 % higher than the reported values, while this ratio reaches to 56% of the soil.  Conclusion: The average indoor radon concentration indoor in Al-Rusaifa exceeds the action radon level recommend by WHO (100 Bq/m3). The potential health impact in this city is considered high. High radon level in Al- Rusaifa may be due to the phosphate content in its soil. A correlation between the radon concentration in the soil and indoor was observed http://ijrr.com/article-1-1823-en.pdf 2016-12-18 367 371 10.18869/acadpub.ijrr.14.4.367 Keywords: Radon passive dosimeter Amman Al- Rusaifa. M.K. Alqadi 1 Department of physics, Jordan University of Science and Technology, Irbid, Jordan AUTHOR F.Y. Alzoubi 2 Department of physics, Jordan University of Science and Technology, Irbid, Jordan AUTHOR M.A. Jaber 3 Department of physics, Jordan University of Science and Technology, Irbid, Jordan AUTHOR
OTHERS_CITABLE Radiological risk analysis of sediment from Kutubdia island, Bangladesh due to natural and anthropogenic radionuclides To assess the environmental radioactivity levels and hence to determine the population exposure in Kutubdia Island, Bangladesh the sediment samples were analyzed by using gamma ray spectrometry. In those sediment samples the average activity concentration of natural radionuclides 238U, 232Th and 40K were found 15.39±1.67, 38.35±0.76 and 475.51±21.15 Bq/kg respectively. The activity concentration of 238U and 232Th were less than the world average. But the activity concentration of 40K was higher than the world average values. These results were used to calculate the radiological hazard parameters like radium equivalent activities (Raeq), representative level index (Iγr). Due to natural radionuclides in sediment, the effective annual outdoor dose in the study area was 0.07 mSv; which is within the accepted range of 0.07 mSv. The average value of radium equivalent activities (Raeq) and representative level index (Igr) were found to be 128.03±12.08 Bq/Kg and 0.96±0.09 Bq/Kg which were greater than the world average. The anthropogenic radionuclide 137Cs was also found in few samples. The average activity concentration of 137Cs was 1.64±0.20 Bq/kg which is lower than the world average. The obtained experimental data of this research work would be useful to assess the population exposure from radionuclides in sediment as well as base line data of natural radioactivity in this island. http://ijrr.com/article-1-1824-en.pdf 2016-12-18 373 377 10.18869/acadpub.ijrr.14.4.373 Keywords: Natural radionuclides HPGe gamma-spectrometry radium equivalent activity representative level index annual effective dose. Q.M. Rashed-Nizam 1 Department of Physics, University of Chittagong, Chittagong-4331, Bangladesh AUTHOR M. Rahman 2 Department of Physics, University of Chittagong, Chittagong-4331, Bangladesh AUTHOR M.K. Tafader 3 Institute of Marine Science, University of Chittagong, Chittagong -4331, Bangladesh AUTHOR M. Zafar 4 Institute of Marine Science, University of Chittagong, Chittagong -4331, Bangladesh AUTHOR A.K.M.S.I. Bhuian 5 Radioactivity Testing and Monitoring Laboratory, Bangladesh Atomic Energy Commission, Chittagong Medical College Campus, Chittagong, Bangladesh AUTHOR R.A. Khan 6 Radioactivity Testing and Monitoring Laboratory, Bangladesh Atomic Energy Commission, Chittagong Medical College Campus, Chittagong, Bangladesh AUTHOR M. Kamal 7 Radioactivity Testing and Monitoring Laboratory, Bangladesh Atomic Energy Commission, Chittagong Medical College Campus, Chittagong, Bangladesh AUTHOR M.I. Chowdhury 8 Radioactivity Testing and Monitoring Laboratory, Bangladesh Atomic Energy Commission, Chittagong Medical College Campus, Chittagong, Bangladesh AUTHOR M.N. Alam 9 Radioactivity Testing and Monitoring Laboratory, Bangladesh Atomic Energy Commission, Chittagong Medical College Campus, Chittagong, Bangladesh AUTHOR
OTHERS_CITABLE Design and fabrication of high density borated polyethylene nanocomposites as a neutron shield Background: Polyethylene composites including boron can be used as an effective neutron shield. Our investigation focuses on manufacturing borated polyethylene nano-composite. The purpose of this study is to design a radiation shield for use in both neutron and gamma fields. Materials and Methods: Borated polyethylene shields containing 2%, and 5% weight percentage of Boron nano-particles were constructed and their neutron attenuation was compared with pure polyethylene. Polycarbonate films were used to find the attenuation of Am-Be neutrons after passing the shields. Mechanical properties of the shields were finally compared. Results: Mean  (± SD) number of α tracks induced by neutrons passing through the shields, were found to be 1.0488×103±128.98,  1.1972×103±289.56and 1.5340×103±206.52 for polyethylene with 5% by weight, polyethylene with 2% by weight boron nano-particles, and pure polyethylene, respectively. The neutron spectrum after each shield was also obtained by MCNP4C Monte Carlo simulations. On the other hand, borated polyethylene nano-composites showed higher tensile strength compared to that of pure polyethylene. Attenuation of neutrons measured in experiments and the result of MCNP simulation were in good agreement. Conclusion: A statistically significant difference was found between neutron attenuation by borated polyethylene nanocomposite made of 5% by weight boron and pure polyethylene. However, the difference between borated polyethylene nano-composite with 5% weight and 2% wt boron was not statistically significant. http://ijrr.com/article-1-1825-en.pdf 2016-12-18 379 383 10.18869/acadpub.ijrr.14.4.379 Keywords: Nano-composites neutron shield borated polyethylene MCNP. S.M.J. Mortazavi 1 Department of Medical Physics and Medical Engineering, and The Center for Research in Radiation Sciences (CRRS), Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR M. Kardan 2 Nuclear Science and Technology Research Institute, Tehran, Iran AUTHOR S. Sina 3 Department of Nuclear Engineering, School of Mechanical Engineering, Shiraz University, Shiraz, Iran AUTHOR H. Baharvand 4 Department of Polymer Chemistry, Iran Polymer Institute, Tehran, Iran AUTHOR N. Sharafi nasrinsharafi@ymail.com 5 Department of Radiology, School of Paramedical Sciences, Shiraz University of Medical Sciences, Shiraz, Iran AUTHOR