en jalali 1393 4 1 gregorian 2014 7 1 12 3 online 1 fulltext

en Background: There is a rapid increase worldwide in the consumption of mineral waters which may contain different level of radioactive elements, especially 226Ra, in addition to varying amounts of beneficial salts. Therefore, a comprehensive study was planned and carried out in order to determine concentration of 226Ra natural radionuclide in bottled mineral waters that commercially available in Marmara Region of Turkey. Materials and Methods: The method used for 226Ra concentration analysis bases on the measurement of Radon (222Rn) coming from 226Ra dissolved in the water. The measurements were performed using RAD 7, a solid state α detector, with RAD H2O accessory manufactured by DURRIDGE COMPANY Inc. Results: The 226Ra concentration in mineral waters was found to vary from <0.074 to 0.625 Bql-1 with an average value of 0.267 Bql-1.The committed effective doses due to ingestion of 226Ra from the one year consumption of these waters were estimated to range from 10.8 to 90 µSvy-1, from 9 to 75 µSvy-1 and from 3.15 to 26.25 µSvy-1, for infants, children and adults, respectively. Conclusion: The results obtained in this study indicate that the committed effective doses are below the WHO (World Health Organization) recommended reference level of 100 µSvy-1. 226Ra activity, mineral water, committed effective dose 193 201 http://ijrr.com/browse.php?a_code=A-10-1-505&slc_lang=en&sid=1 2014/08/22 1393/5/31 2014/08/22 1393/5/31 E. Tabar Sakarya University, Faculty of Science and Art, Department of Physics, Sakarya, Turkey etabar@sakarya.edu.tr 0031947532846009479 0031947532846009479 Yes H. Yakut Sakarya University, Faculty of Science and Art, Department of Physics, Sakarya, Turkey 0031947532846009480 0031947532846009480 No

en Background: Ovarian immature teratoma is a very rare type of tumor associated with a high relapse rate and mortality. Correspondingly, early diagnosis is important for effective treatment. The goal of this study was to retrospectively analyze the ultrasound characteristics of 11 cases of immature teratomas. Materials and Methods: Between January 2002 and December 2010, 11 patients were diagnosed with pathologically confirmed immature teratomas. Patients enrolled in this study underwent a transabdominal ultrasound examination prior to surgery. Tumor size, shape, internal echo, calcification, cystic degeneration, and blood flow for each immature teratoma were analyzed. Levels of alpha fetal protein (&alphaFP) were also evaluated. Results: The average tumor size was 8 cm (range, 4–13). Echo patterns obtained included mixed echo (n = 7), solid echo (n = 2), and cystic echo (n = 2). Coarse calcifications were detected in five cases, while blood flow signal was detected in one case, and ascites were detected in three cases. Only one case had elevated levels of &alphaFP. Conclusion: Ultrasound imaging of immature teratomas detected large tumors that were predominantly involved mixed-echo masses, cystic degeneration, and coarse calcification on the cavity wall. In some cases, blood flow signal was detected in the mass and ascites were present in the abdominal cavity. mmature teratoma, ultrasound, calcification, alpha-fetal protein 203 209 http://ijrr.com/browse.php?a_code=A-10-1-506&slc_lang=en&sid=1 2014/08/222014/08/22 1393/5/31 2014/08/222014/08/22 1393/5/31 Z.Y. Shen Department of Radiology, Nantong Tumor Hospital, No. 30, North Tongyang Road, Nantong, Jiangsu, China 226361 ntrgszy103@163.com 0031947532846009481 0031947532846009481 Yes B. Hu Department of Ultrasound in Medicine, Shanghai Institute of Ultrasound in Medicine, Shanghai Jiaotong University Affiliated Sixth People’s Hospital, Shanghai, China 200233 0031947532846009482 0031947532846009482 No G.L. Xia Department of Radiology, Nantong Tumor Hospital, No. 30, North Tongyang Road, Nantong, Jiangsu, China 226361 0031947532846009483 0031947532846009483 No K. Shen Department of Radiology, Nantong Tumor Hospital, No. 30, North Tongyang Road, Nantong, Jiangsu, China 226361 0031947532846009484 0031947532846009484 No

en Background: Most of the cytogenetic dosimetry, except Premature Chromosome Condensation assay, saturates at 6 Gy. Present studies are aimed to assess feasibility of simple CB-MN assay for prescreening of high dose accidental exposures. Materials and Methods: Human peripheral blood lymphocytes from two donors were gamma irradiated to different doses ranging from 0-15Gy, cultured for 72 h. Cytochalasin-B was added to the cultures at 44 h. Slides were analyzed for frequency of Mononucleated cells (MNC), ratio of Tri/Quadra nucleated cells, micronuclei ( MN ) yield in MN positive cells, mitotic bridges and apoptosis. Results: At 5 Gy 67% Mononucleated cells, 0.22% apoptotic cells and 1.76% mitotic bridges were observed. Micronuclei yield in MN positive binucleated cells was found to be 1.43±0.04. At 8Gy 96.63% Mononucleated cells, 22.64% apoptotic cells and 3.8% mitotic bridges were observed. Micronuclei yield in MN positive binucleated cells was found to be 2.18±0.18. At 15 Gy, 99.6% of the cells were Mononucleated and 0.38% was binucleated and MN yield was 2.9 ±0. The total number of MN in MN positive cells increases with increasing radiation doses. Conclusion: All the three indicators number of MN in all binucleated cells (BNC) , number of MN /MN positive binucleated cells and the nuclear division index (NDI) can serve as good biomarkers for biodosimetry at high doses. Although the frequency of mitotic bridges and apoptotic bodies increases with dose, there is no consistent difference between various doses. Thus the CBMN + NDI assay can be a biodosimetry method at high doses. CB, MN assay, biodosimetry, high dose exposures 211 215 http://ijrr.com/browse.php?a_code=A-10-1-507&slc_lang=en&sid=1 2014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/22 1393/5/31 K. Shirsath Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400 085, India 0031947532846009485 0031947532846009485 No N. Bhat Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400 085, India 0031947532846009486 0031947532846009486 No K. Anjaria Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400 085, India 0031947532846009487 0031947532846009487 No U. Desai Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400 085, India 0031947532846009488 0031947532846009488 No S. Balakrishnan Radiological Physics and Advisory Division, Bhabha Atomic Research Centre, Trombay, Mumbai-400 085, India bsdevi@barc.gov.bsdevi@barc.gov.bsdevi@barc.gov.in 0031947532846009489 0031947532846009489 Yes

en Background: Finding a suitable method for rapid, accurate and reliable estimation of absorbed dose has high priority in management of the radiation exposed persons. Shortly after radiation exposure, apoptosis is a major detriment in proliferative tissues such as the hematopoietic system. Therefore, quantification of apoptosis in these tissues could be useful for rapid estimation of radiation exposure. Annexin V (ANX) is considered as a biological probe for detection of apoptotic cells. The aim of the present study is to investigate the potential suitability of apoptosis quantification for estimation of radiation exposure. Materials and Methods: In order to determine the biological distribution of ANX within the mice body after radiation exposure, mice whole body irradiated with 2, 4, 6 and 8 Gy (60Co gamma rays). Ten hours later, ANX conjugated with super paramagnetic iron oxide nanoparticles (SPIO-ANX) was administered intravenously and magnetic resonance imaging was conducted 3 hours later. Results: Average signal intensities in the regions of interest (ROIs) of the femur bone marrow, liver and testis were calculated and normalized to parafemoral muscle signals. SPIO-ANX accumulated in bone marrow of irradiated groups and significantly decreased the normalized mean of signal intensity for bone marrow in comparison with control group (p< 0.01). Conclusion: Tracing and quantification of SPIO-ANX in bone marrow can be used as an indicator for radiation exposure. However, development and optimization of the assay are necessary for discrimination between different radiation doses. Apoptosis, radiation exposure, magnetic resonance imaging, dose estimation, annexin V 217 222 http://ijrr.com/browse.php?a_code=A-10-1-508&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/22 1393/5/31 Gh. Haeri Department of Medical Physics, Faculty of Medical Sciences, Tarbiat Modares University, Tehran, Iran 0031947532846009490 0031947532846009490 No H. Rajabi Department of Medical Physics, Faculty of Medical Sciences, Tarbiat Modares University, Tehran, Iran hRajabi@modares.ac.ir 0031947532846009491 0031947532846009491 Yes Sh. Akhlaghpoor Department of Radiology, Sina Hospital, Tehran University of Medical Science, Tehran, Iran 0031947532846009492 0031947532846009492 No

en Background: Radiation-induced lung injury is a refractory side effect in lung cancer radiotherapy, the mechanism still remains unclear, hence an appropriate animal mode may become useful to investigate it. Materials and Methods: 50 female Wistar rats were randomly divided into 5 groups, average 10 rats/cage: A. control group B. 3Gy×10f C. 6Gy×5f D. 12.5Gy×1f E.15.3Gy×1f. By different doses of radiation to the right lung of rats under American Varian linear accelerator, all the rats were executed at 30days after irradiation, lung tissues were collected to observe the pathological changes by HE staining , and additional lung tissues were extracted mRNA to measure gene expression of TNF-a and IL-18 by qRT-PCR. Results: In contrast to the control group, congestion, gore, edema, broadening alveolar interval and the bulla can be observed after irradiation. 3Gy×10f radiation led to most rat death because of frequent anaesthesia. 12.5Gy×1f radiation induced mild lung injury. 6Gy×5f and 15.3Gy×1f radiation induced remarkable lung injury. However, 15.3Gy×1f was seldom adopted in clinical settings. The measurement of cytokine variation by qRT-PCR also indicated that 6Gy×5f radiation stimulated the most obvious elevation of IL-18, while 15.3Gy×1f radiation elevated TNF-a most. Conclusion: A rat model of radiation-induced lung injury was appropriately established, 6Gy×5f radiation was the most suitable radiation method for establishing this rat model. Rat, radiation, lung injury, model 223 227 http://ijrr.com/browse.php?a_code=A-10-1-509&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 S Qibin Cancer Center, Renmin Hospital of Wuhan University, Wuhan 430060, China 347952582@qq.com 0031947532846009493 0031947532846009493 Yes H. Weiguo Cancer Center, Renmin Hospital of Wuhan University, Wuhan 430060, China 0031947532846009494 0031947532846009494 No C. Yuxin Cancer Center, Renmin Hospital of Wuhan University, Wuhan 430060, China 0031947532846009495 0031947532846009495 No Xubin Cancer Center, Renmin Hospital of Wuhan University, Wuhan 430060, China 0031947532846009496 0031947532846009496 No C. Hao Cancer Center, Renmin Hospital of Wuhan University, Wuhan 430060, China 0031947532846009497 0031947532846009497 No

en Background: Vitamin D, especially its most active metabolite 1,25-dihydroxyvitamin D₃(Vit D) is essential in regulating a wide variety of biologic processes, such as regulating mesangial cell activation. The objective of this study was to assess the histopathological changes of effectiveness of Vit D as a protective agent against radiation induced lung injury. Materials and Methods: Eighteen Wistar rats were divided into three groups: control group (group 1:4 rats), irradiation alone group (group 2:7 rats) and irradiation+vit D (group 3:7 rats). Rats in group 2 and 3 were exposed to 20 Gy radiations to the right lung in a Co60 radiotherapy machine under general anesthesia. Additionally, rats in group 3 received Vit D at a single dose of 0.2 mcg injected IM 2 hours before exposure to irradiation. Rats were sacrificed and lungs were dissected fifty days after post-irradiation. Myofibroblasts and vitamin D₃receptors (VDR) in extracted lungs were stained by immunohistochemistry using alpha-smooth muscle actin (SMA) and VDR antibodies. Blinded histological evaluation was performed to assess lung injury. Lung injury was assessed by the acute lung injury score and myofibroblastic differentiation score. Results: Acute lung injury scores and myofibroblastic differentiation scores were significantly lower in the radiation+vit D group compared to irradiation alone group (p=0.001 and p=0.001, respectively). Conclusion: This study indicates that administration of vit D plays a protective role against acute lung injury through blocking myofibroblastic differentiation. Radiation, lung injury, vitamin D, VDR, calcitriol, fibrosis 229 233 http://ijrr.com/browse.php?a_code=A-10-1-510&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 F. Bir Pamukkale University, Faculty of Medicine, Department of Pathology, Denizli, Turkey fbir@pau.edu.tr 0031947532846009498 0031947532846009498 Yes B. Baltalarlı Pamukkale University, Faculty of Medicine, Department of Radiation Oncology, Denizli, Turkey 0031947532846009499 0031947532846009499 No G. Abban Pamukkale University, Faculty of Medicine, Department of Histology, Denizli, Turkey 0031947532846009500 0031947532846009500 No N. Demirkan Pamukkale University, Faculty of Medicine, Department of Pathology, Denizli, Turkey 0031947532846009501 0031947532846009501 No

en Background: This research was conducted to evaluate the potential benefits of zinc sulphate in the prevention of radiation induced mucositis in patients who are being treated for head and neck cancers. Materials and Methods: Forty patients with proven cancers of head and neck were randomly divided into 2 equal groups that either received zinc sulphate or placebo (control group). Patients who received curative radiotherapy or chemoradiotherapy were instructed to take zinc sulphate capsules (30 mg) daily at 8 hours interval. They were to begin 10 days before the start of treatment and continued until 2 weeks after completing the schedule. Mucositis was evaluated weekly according to the Oral Mucositis Assessment Scale (OMAS). Results: In both groups (zinc and control) mucositis was evident during the first week but its prevalence was 40% and 70.5% in the zinc and placebo groups respectively at the end of this period. This difference was significant (p<0.0001). The mean severity of oropharyngeal mucositis increased after commencement of radiotherapy and reached to maximum intensity in the 4th week. Control group showed higher severity (p<0.0001). In comparison with the placebo group, the mucositis score of OMAS in the zinc group was lower until at 2 weeks after end of the treatment (p=0.0001). Conclusion: The present study shows that Zinc sulfate is effective in reducing the severity of radiation induced oropharyngeal mucositis. In addition, it delays the development of mucositis and may be used at a lower dose (30 mg 3 times daily) with the same benefit but fewer side effects. Zinc sulfate, mucositis, radiotherapy, prevention 235 241 http://ijrr.com/browse.php?a_code=A-10-1-511&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 D. Moslemi Division of Radiation Oncology, School of Medicine, Babol University of Medical Sciences, Babol, Iran 0031947532846009502 0031947532846009502 No N. Babaee Department of Oral Medicine, School of Dentistry, Babol University of Medical Sciences, Babol, Iran 0031947532846009503 0031947532846009503 No M. Damavandi Department of Oral Medicine, School of Dentistry, Babol University of Medical Sciences, Babol, Iran 0031947532846009504 0031947532846009504 No M. Pourghasem Department of Anatomy, Embryology and Histology, Babol University of Medical Sciences, Babol, Iran mpourghasem@hotmail.com 0031947532846009505 0031947532846009505 Yes A.A. Moghadamnia Department of Pharmacology, School of Medicine, Babol University of Medical Sciences, Babol, Iran 0031947532846009506 0031947532846009506 No

en Background: The aim of this study was to evaluate the reduction in excision cavity volume (ECV) during the whole breast radiotherapy (WBRT). The delineating of reduced cavity volume on secondary CT (computed tomography) might decrease the field size of boost plan. Materials and Methods: Twenty patients were treated having breast conservative surgery. At first, primary CT simulation (CT-1) was done prior to WBRT. Treatment planning was performed by a 3D treatment planning system. A CT-2 was performed after WBRT. Then the excision cavity was contoured on CT-1 and CT-2 for each patient. Boost irradiation was planned on both ECV-1 and ECV-2. Results: In Comparison of CT-1 and CT-2: The contoured volumes for ECV-1 and ECV-2 were on average of 42.9 cm3and 23.4 cm3, respectively (p< 0.002). The ECV-2 was reduced in 85% of the patients. Patients with ECV-1 greater than the mean value of ECV-1 (ECV-1> 35.5 cm3) had more reduction in ECV-2 than patient with ECV-1 smaller than the mean value (p < 0.000). The volume of normal breast tissue on CT-2 was decreased from the volume of CT-1 (p< 0.03). Conclusion: A significant reduction in excision cavity volume was shown during WBRT. This volume reduction made smaller sizes of boost field and remaining breast received lower doses. The reduction was more significant in patient with primary large ECV. The Secondary CT for boost planning is suggested for patients with larger cavities after WBRT. Excision cavity volume (ECV), secondary CT, whole breast radiotherapy (WBRT) 243 248 http://ijrr.com/browse.php?a_code=A-10-1-512&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 A.R. Nikoofar Parsa Radiotherapy Center, Pars Hospital, Tehran, Iran 0031947532846009507 0031947532846009507 No Z. Falahatpour Medical Radiation Engineering of Faculty of Shahid Beheshti University, Tehran, Iran mahsa_falahat@yahoo.com 0031947532846009508 0031947532846009508 Yes G.H. Hoseinzadeh Tehran University Medical Sciences, Tehran Iran 0031947532846009509 0031947532846009509 No

en Background: Physical wedges are still widely used as beam modifiers in external beam radiotherapy. However the presence of them in the beam trace may cause beam hardening which may not be considered in many treatment planning systems. The aim of this study is to investigate the beam hardening effect generated by physical wedges via different beam quality indexes as photon spectrum, half value layer, mean energy and tissue–phantom ratio. Materials and Methods: The effect of physical wedges on the photon beam quality of a 6-18MV Varian 2100C/D accelerator was studied with the BEAMnrc Monte Carlo code. Good agreements were obtained between measured and calculated depth doses and beam profiles for open and wedged photon beams at both energies. Results: It was noticed that for 6 MV photon beams, physical wedges have more significant effects on beam quality than for 18 MV. Also it was obtained that at 18 MV photon beam as the wedge angle increased, the effect of wedge on beam quality becomes reversed and beam softening occurred. Conclusion: According to these results, it is recommended that beam hardening and softening of physical wedges should be considered in treatment planning systems in order to increase the accuracy in dose delivery. Monte Carlo, beam hardening, physical wedge 249 256 http://ijrr.com/browse.php?a_code=A-10-1-513&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 Gh. Geraily Department of Medical Physics, Tehran University of Medical Science, Tehran, Iran 0031947532846009510 0031947532846009510 No M. Mirzapour Department of electronic, East Tehran Branch, Islamic Azad University, Tehran, Iran 0031947532846009511 0031947532846009511 No S.R. Mahdavi Department of Medical Physics, Tehran University of Medical Science, Tehran, Iran srmahdavi@hotmail.com 0031947532846009512 0031947532846009512 Yes M. Allahverdi Department of Medical Physics, Tehran University of Medical Science, Tehran, Iran 0031947532846009513 0031947532846009513 No A. Mostaar Department of Biomedical Engineering and Medical Physics, Shahid Beheshti University of Medical Science, Tehran, Iran 0031947532846009514 0031947532846009514 No M. Masoudifar Department of Radiation Oncology, Mahak Hospital, Tehran, Iran 0031947532846009515 0031947532846009515 No

en Background: Electronic portal imaging devices (EPIDs) play an important role in radiation therapy portal imaging, geometric and dosimetric verifications. A successful utilization of EPIDs for imaging and dosimetric purposes requires a reliable quality control process routine to be carried out regularly. In this study, two in-house phantoms were developed and analyzed for implementation in a quality assurance program for dosimetry purposes. Materials and Methods: An amorphous silicon (a-Si) imager (OptiVue500) was used. A low contrast resolution phantom and an image quality phantom were constructed and implemented. Low contrast resolution of the EPID was evaluated by counting the number of holes detectable in the image of phantom using human observers and a software. The image quality phantom was used for modulation transfer function, contrast to noise ratio and noise level evaluations. This phantom contains five sets of high-contrast rectangular bar patterns of variable spatial frequencies and six uniform regions. Results: Although the manual low contrast resolution method was observer-dependent and insensitive to artifacts, the automatic method was robust and fully objective but sensitive to artifacts. The critical frequency values for 6 and 18 MV were 0.3558±0.006 lp/mm and 0.2707±0.006 lp/mm respectively. The contrast-to-noise ratio was found to be ~ 240% higher for 6 MV compared to 18 MV. Conclusion: The developed phantoms provide a convenient process for periodic performance of an EPID. These phantoms are independent of the EPID system and provide robust tools for continuous monitoring of image quality parameters as well as dosimetric parameters. Electronic portal imaging device, quality assurance, phantom 257 264 http://ijrr.com/browse.php?a_code=A-10-1-514&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 A. Jomehzadeh Medical Physics Department, Isfahan University of Medical Sciences, Isfahan, Iran jomehzadeh@rums.ac.ir 0031947532846009516 0031947532846009516 Yes P. Shokrani Medical Physics Department, Isfahan University of Medical Sciences, Isfahan, Iran 0031947532846009517 0031947532846009517 No M. Mohammadi Medical Physics Department, Hamadan University of Medical Sciences, Hamadan, Iran 0031947532846009518 0031947532846009518 No A. Amouheidari Radiation Oncology Department, Isfahan Milad Hospital, Isfahan, Iran 0031947532846009519 0031947532846009519 No

en Background: The purpose of this project was to derive the brachytherapy dosimetric functions described by American Association of Physicists in Medicine (AAPM) TG-43 U1 based on high dose rate 192I sources. Materials and Methods: The method utilized included both simulation of the designed Polymethyl methacrylate (PMMA) phantom using the Monte Carlo of MCNP4C and benchmarking of the simulation with thermoluminescent (TL) dosimeters. Results: The obtained results for the radial dose function and anisotropy function showed nominal errors of less than 3% between TL measurements and the MCNP4C results. Conclusion: It may be concluded that due to small observed errors and the large uncertainty associated with the high dose gradients near the source point the simulation results can be used for dose estimation. Brachytherapy, 192Ir flexisource, MCNP calculation, radiation dosimetry 265 270 http://ijrr.com/browse.php?a_code=A-10-1-515&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 N. Babaei Bidmeshki Department of Energy Engineering, Sharif University of Technology, P.O. Box 1485893169, Tehran, Iran 0031947532846009520 0031947532846009520 Yes M. Sohrabpour Department of Energy Engineering, Sharif University of Technology, P.O. Box 1485893169, Tehran, Iran 0031947532846009521 0031947532846009521 No S.R. Mahdavi Department of Medical Physics, Faculty of Medicine, Tehran University of Medical Sciences P.O. Box 1449614525, Tehran, Iran 0031947532846009522 0031947532846009522 No

en Background: The aims of the study are to determine the radioactivity concentrations of 226Ra, 238U, 232Th and 40K in vegetables of a recently found high background radiation area of south-eastern part of Bangladesh and to detect the radiological risks to human from intake of these vegetables. Materials and Method: 10 plant samples were collected randomly from different locations of the study area. The radio-nuclides in papaya were measured by direct &gamma-ray spectrometry using HPGe detector. Results: The average activity concentrations of 226Ra, 238U, 232Th and 40K in papaya samples were 80.95±13.61, 64.77±38.47, 83.53±20.50 and 1691.45±244.98 Bq kg-1 respectively. The annual effective ingestion dose due to intake of papaya was 1.1 mSv Y-1. Conclusion: The concentrations of radio-nuclides in the papaya samples found in present study were higher than the world average values suggested by the UNSCEAR. The annual effective ingestion dose was found 3.8 times higher than total exposure per person resulting from the ingestion of terrestrial radioisotopes. Natural radioactivity, vegetables, HPGe detector, effective ingestion dose 271 275 http://ijrr.com/browse.php?a_code=A-10-1-516&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 A. Islam Department of Environmental Sciences, Jahangirnagar University, Savar, Dhaka-1342, Bangladesh ashnaislam@live.com 0031947532846009523 0031947532846009523 Yes A. Begum Health Physics Division, Atomic Energy Centre, Dhaka-1000, Bangladesh 0031947532846009524 0031947532846009524 No S. Yeasmin Health Physics Division, Atomic Energy Centre, Dhaka-1000, Bangladesh 0031947532846009525 0031947532846009525 No M.S. Sultana Department of Environmental Sciences, Jahangirnagar University, Savar, Dhaka-1342, Bangladesh 0031947532846009526 0031947532846009526 No

en Background: High density concrete is extensively used for efficient radiation attenuation in radiotherapy rooms and nuclear reactors. Over the past eight years, some efficient galena-based concrete samples for shielding X or gamma rays was produced. The goal of this study was to produce a novel high density concrete against neutron and photon radiations using tourmaline and galena. Materials and Methods: Attenuation of gamma photons was measured using a Farmer type ionization chamber with a standard 60Co buildup cap on a Theratron 60Co therapy unit. Neutron shielding characteristics were measured by using an Am-Be source. The MCNP4C radiation transport computer code was used to investigate the effects of various shield thicknesses on the attenuation of gamma-ray photons and neutrons. Results: The concrete samples had a density of 4.0- 4.2 g/cm3. The compressive strength was 326 - 560 kg/cm2. The calculated value for Half Value Layer (HVL) of the tourmaline-galena concrete samples for 60Co gamma rays was 2.72 cm, which is much less than that of ordinary concrete (6.0 cm). The MC-derived HVL for photons with the same energy was 2.77 cm, which is in a good agreement with the experimental data. Moreover, ToGa concrete had up to 10 times greater neutron attenuation compared to that of the reference concrete. Conclusion: Tourmalin-Galena Concrete opens a new horizon in economic and efficient gamma/neutron shielding in high-energy radiotherapy bunkers, nuclear power plants, and shielding of radioactive sources. Heavy concrete, boron rich mineral, radiation shielding, Monte Carlo simulation 277 282 http://ijrr.com/browse.php?a_code=A-10-1-517&slc_lang=en&sid=1 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 2014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/222014/08/22 1393/5/31 S.M.R. Aghamiri Radiation Medicine Department, Shahid Beheshti University, Tehran, Iran 0031947532846009527 0031947532846009527 No S.M.J. Mortazavi Medical Physics Department, School of Medicine, Shiraz University of Medical Sciences, Shiraz, Iran 0031947532846009528 0031947532846009528 No M.A. Mosleh Shirazi Physics Unit, Radiotherapy Department, Shiraz University of Medical Sciences, Shiraz, Iran 0031947532846009529 0031947532846009529 No M. Baradaran-Ghahfarokhi Medical Physics and Medical Engineering Department, School of Medicine, Isfahan University of Medical Sciences, Isfahan, Iran 0031947532846009530 0031947532846009530 No F. Rahmani Department of Physics, KNT university of Technology, Tehran, Iran 0031947532846009531 0031947532846009531 No A. Amiri Chemical Engineering Department, New Mexico State University, Las Cruces, New Mexico, USA 0031947532846009532 0031947532846009532 No S. Jarideh Ionizing and Non-ionizing Radiation Protection Research Center, Shiraz University of Medical Sciences, Shiraz, Iran sjarideh726@gmail.com 0031947532846009533 0031947532846009533 Yes