@article{ author = {Bhardwaj, A.K. and Kehwar, T.S. and Chakarvarti, S.K. and Oinam, A.S. and Sharma, S.C.}, title = {3-Dimensional conformal radiotherapy versus intensity modulated radiotherapy for localized prostate cancer: Dosimetric and radiobiologic analysis}, abstract ={ Background: To analyze the dosimetric and radio biologic advantages between intensity modulated radiotherapy (IMRT) and 3 dimensional conformal radiotherapy (3DCRT) and selection of optimal photon energy for IMRT treatments. Material and methods: 24 patients with localized prostate carcinoma were planned for 3DCRT and IMRT techniques. Radiation dose of 54 Gy with 2 Gy/fraction, was planned to Planning target volume (PTV1) (prostate + seminal vesicle + 1 cm margin) and 72 Gy to PTV2 (prostate + 1 cm margin) respectively. 3DCRT planning was done using 15 MV photon beam while IMRT plans were created using 6 MV and 15MV photons. Treatment plans were analyzed using mean, median, dose maximum and cumulative dose volume histogram for PTV1, PTV2, bladder, and rectum. Tumor control probability (TCP) was calculated for prostate. Normal tissue complication probability (NTCP) was calculated for bladder, rectum, and head of femur. Results: Mean dose to prostate was 72.79 ± 0.18 Gy for IMRT 15 MV, 72.16 ± 0.27 Gy for 3DCRT and 72.48 ± 0.19 Gy for IMRT 6 MV. TCP was greater for IMRT 15 MV followed by IMRT 6 MV. The mean value of NTCP was significantly lower (p = 0.0015) for IMRT 6 MV compared to 3DCRT for rectum while for bladder all were comparable.  Conclusion: IMRT techniques shows superiority in sparing surrounding critical organs, thus reducing normal tissue complication rates while maintaining the same or higher tumor control probability. No significant difference was observed between IMRT 6 MV and IMRT 15 MV techniques.}, Keywords = {3DCRT, IMRT, TCP, NTCP.}, volume = {5}, Number = {1}, pages = {1-8}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-287-en.html}, eprint = {http://ijrr.com/article-1-287-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Mozdarani, H. and Taheri, A. and Haeri, S.A.}, title = {Assessment of the radioprotective effects of amifostine on human lymphocytes irradiated in vitro by gamma-rays using cytokinesis-blocked micronucleus assay}, abstract ={  Background: A radioprotective effect of amifostine as well as its ability to modulate the level of spontaneous and gamma-irradiation-induced genetic changes on human peripheral blood lymphocytes has been investigated . Amifostine, known as a potent radical scavenger, has been introduced as the most effective radioprotector, yet it is not completely approved for the clinical use. However, further in vitro and clinical studies are needed to clarify its mechanisms of action.   Materials and Methods : Whole blood samples from healthy donors were exposed to various doses of gamma-rays. Lymphocytes in cultures were treated with amifostine at different concentrations (2, 4 and 6 mM) in the presence or in the absence of 1 IU/ml alkaline phosphatase before or after gamma-irradiation. Standard procedure for the cytokinesis-block micronucleus (CBMN) assay was used to assess the effect of amifostine on radiation induced micronucleus in binucleate lymphocytes.     Results : Irradiated blood samples showed an increase in the total number of micronuclei (MN) significantly different from controls (p<0.05). However, pre-treatment of lymphocytes with amifostine in the presence of alkaline phosphatase, 15 minutes before irradiation, led to a significant decrease in the frequencies of MN and cells with more than one MN (p<0.05). Amifostine, in its own, produced little or no protection. However, the addition of amifostine with alkaline phosphatase to the cell cultures 15 minutes after irradiation produced substantial radioprotection significantly different from the frequencies of MN induced by radiation alone (p<0.05).   Conclusion : Results clearly indicated that gamma-rays induced MN in lymphocytes in a dose dependent manner. The highest protective effect was achieved when amifostine was phosphorilated by alkaline phosphatase and present before irradiation in the cellular environment, indicating its radical scavenging mechanism of radioprotection. Since the administration of amifostime after irradiation also led to a considerable decrease in the frequency of radiation induced MN, which might be possible for other mechanisms such as induction of cell cycle delay and hence influencing DNA repair, are involved in radioprotection by amifostine.}, Keywords = {Amifostine, gamma-rays, radioprotection, human lymphocyte, micronuclei.}, volume = {5}, Number = {1}, pages = {9-16}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-288-en.html}, eprint = {http://ijrr.com/article-1-288-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Manigandan, and Selvasekarapandian, and Manikandan,}, title = {Distribution of radionuclide in the forest soils (Western Ghats-India)}, abstract ={Background: The presence of radionuclides in the soil, measures need to be taken to minimize the radiation dose to humans. It is mostly gamma-emitting radionuclides that contribute to the radiation dose in long term behavior of these radionuclides in soil may determine the extent to which such countermeasures need to be applied. Materials and Methods: The activity concentration of these radionuclides in the soil samples that collected from the Longwood forest at western Ghats have been analyzed using Gamma spectrometry. Results: The mean activities of 238U, 232Th and 40K were observed 26.261Bq/kg, 53.614 Bq/kg, 204.084 Bq/kg, dry weight, respectively. The average value of dose rate was calculated 55.48 nGy/h by applying the conversion factor where as the environmental dosimeter shows the absorbed dose rate at 1m high is 96.96 nGy/h. Conclusion: It was observed that the activity concentration of primordial radionuclides and the gamma dose rate measurements by ERD and from soil is relatively higher than world average.}, Keywords = {238U, 232Th and 40K, Western Ghats- South India, absorbed dose, ERD, monazite, Igneous rock.}, volume = {5}, Number = {1}, pages = {17-22}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-289-en.html}, eprint = {http://ijrr.com/article-1-289-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Mesbahi, A. and Mehnati, P. and Keshtkar, A.}, title = {A comparative Monte Carlo study on 6MV photon beam characteristics of Varian 21EX and Elekta SL-25 linacs}, abstract ={Background: Monte Carlo method (MC) has played an important role in design and optimization of medical linacs head and beam modeling. The purpose of this study was to compare photon beam features of two commercial linacs, Varian 21EX and Elekta SL-25 using MCNP4C MC code. Materials and Methods: The 6MV photon beams of Varian 21EX and Elekta Sl-25 linacs were simulated based on manufacturers provided information. Photon energy spectra and absolute absorbed dose values were calculated for field sizes of 10×10 and 20×20 cm2. Also, contamination electron spectra for field size of 20 ×20 cm2 were scored for both linacs.Results: Our results showed that the relative absorbed dose values and contamination electron spectrum were similar and comparable, but photon fluence and absolute absorbed dose values were 17% and 13% higher for Varian linac respectively for the field size of 10×10 cm2.Conclusion: Despite the differences in head components of two commercial linacs, their relative depth dose values were very close to each other. The absolute dose per incident electron showed some discrepancy, as well. Thus, this study suggests the use of absolute absorbed dose values as an invaluable factor when different linacs head are compared using Monte Carlo Method.}, Keywords = {Dosimetric features, Elekta SL-25, Varian 21EX, Monte Carlo method.}, volume = {5}, Number = {1}, pages = {23-30}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-290-en.html}, eprint = {http://ijrr.com/article-1-290-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Esnaashari, K.N. and Allahverdi, M. and Gharaati, H. and Shahriari, M.}, title = {Comparison of measured and Monte Carlo calculated dose distributions from “circular collimators” for radiosurgical beams}, abstract ={Background: Stereotactic radiosurgery is an important clinical tool for the treatment of small lesions in the brain, including benign conditions, malignant and localized metastatic tumors. A dosimetry study was performed for Elekta ‘Synergy S ’ as a dedicated Stereotactic radiosurgery unit, capable of generating circular radiation fields with diameters of 1-5 cm at isocentre using the BEAM/EGS4 Monte Carlo code. Materials and Methods: The linear accelerator Elekta “Synergy S” equipped with a set of 5 circular collimators from 10 mm to 50 mm in diameter at isocentre distance was used. The cones were inserted in a base plate mounted on the collimator linac head . A PinPoint chamber and Wellhofer water tank chamber were selected for clinical dosimetry of 6 MV photon beams. The results of simulations using the Monte Carlo system BEAM/EGS4 to model the beam geometry were compared with dose measurements . Results: An excellent agreement was found between Monte Carlo calculated and measured percentage depth dose and lateral dose profiles which were performed in water phantom for circular cones with 1, 2, 3, 4 and 5 cm in diameter. The comparison between calculation and measurements showed up to 0.5 % or 1mm difference for all field sizes. The penumbra (80-20%) results at 5 cm depth in water phantom and SSD=95 ranged from 1.5 to 2.1 mm for circular collimators with diameter 1 to 5 cm . Conclusion: This study showed that BEAMnrc code has been accurate in modeling Synergy S linear accelerator equipped with circular collimators.}, Keywords = {Monte Carlo , dosimetry, radiosurgery, circular cones.}, volume = {5}, Number = {1}, pages = {31-36}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-291-en.html}, eprint = {http://ijrr.com/article-1-291-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {ShabestaniMonfared, A. and Abdi, R. and Saber, M.A.}, title = {Repeat analysis program in radiology departments in Mazandaran province- Iran Impact on population radiation dose}, abstract ={Background: The rejected films in radiography may be responsible for an unnecessary increase in the radiation dose to the population. The effective dose to population is a very important factor in estimation of stochastic risk in radiology. The main goal of this study was to determine the effective dose to members of the public due to rejected films in diagnostic radiology departments in the Northern province Mazandaran- of Iran. Materials and Methods: A repeat analysis program was set in all radiology departments in Mazandaran province (population = 2976219 person) to determine the total number and type of rejected films. All repeat and discarded films were collected and separated into types according to the etiology leading to their being discarded. Considering technical data about various radiological procedures and using the standard dosimetry tables, the annual effective dose per caput as well as annual gonadal dose per caput due to image retake was estimated. Results: The total number of rejected radiographs in one year period was 73857 (overall reject rate ~ 11.15%) which led to 34.91 µSv and 37.17 µGy as annual average effective dose to a member of the public and annual average gonadal dose per caput respectively. The main reason of retaking the images was improper exposure factors. Conclusion: The reject rate was in the middle range of similar values in other studies whereas in the present study the main reason for rejection was improper exposure factors (67.11%), the main reason for radiography repeat film was different in various countries. Comparing to the estimated 2.4 mSv from natural background radiation , the average annual effective dose and annual average gonadal dose per caput due to repeat/retake films are negligible. However, reducing the reject films is economically rewarding. Further national studies are suggested.}, Keywords = {}, volume = {5}, Number = {1}, pages = {37-40}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-292-en.html}, eprint = {http://ijrr.com/article-1-292-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Kakavand, and Ghafourian, and Haji-Shafeieha,}, title = {Designing an Am-Be miniature neutron source}, abstract ={Background: Miniature neutron sources with high neutron flux have abundant applications in medicine, industry and researches. The most important general characteristic of miniature neutron sources is their diameter which is 3mm in average. In this research, we have surveyed and designed an Am-Be miniature neutron source fabrication. Materials and Methods: This investigation resulted in creation of an Am-Be neutron source, using beryllium metal powder with 98% carat and 100-200 |µm mesh and Americium source with activity of about 200 |µCi. Neutron source designing was performed under safety and protective factors. The system was designed in two different forms based on the fluent yield of neutron or cut off neutron yield. Results: The mean neutron flux of miniature neutron source was measured as 1.14 (n/sec.cm2), and it was calculated as 2.56 (n/sec.cm2) by MCNP (4C) code. Due to purity and mesh of beryllium, which were not calculated by MCNP code, the calculated flux via Monte Carlo method was approximately 2 times larger than neutron flux from fabricated miniature neutron sources. Conclusion: In order to fabricate the miniature neutron sources Am- Be with high efficiency, the americium sources with high activity and the target material (Be) in different forms are required.}, Keywords = {Miniature neutron source, MCNP (4C) Code, BF3 detector, neutron flux, activity.}, volume = {5}, Number = {1}, pages = {41-44}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-293-en.html}, eprint = {http://ijrr.com/article-1-293-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Miri-Hakimabad, H. and Panjeh, H. and Vejdani-Noghreiyan, A.}, title = {Shielding studies on a total-body neutron activation facility}, abstract ={Background: Prompt gamma neutron activation analysis (PGNAA) is known as a non-invasive technique capable of measuring elemental concentration in voluminous samples in a short period of time. Also it is a valuable diagnostic tool for total body elemental measurements. 252Cf and 241Am-Be sources which are usually used in this method, generate not only neutrons, but also emit high-energy and unwanted gamma-rays. Because the patient must be located against the neutron source, patient dose during an analysis is an important concern when using this technique.Materials and Methods: Gamma-rays were attenuated without losing the neutron flux or significant alteration in the neutron spectrum. A relatively safe body chemical composition analyzer was designed with an optimal spherical gamma-ray shield, enclosed to the neutron source. Effects of gamma-ray shielding and optimum radius of spherical Pb shield was investigated and compared with the unfiltered bare source, using MCNP4C code. Then, the gamma ray dose equivalent per source neutron rate (user defined parameter) in the soft tissue is calculated for different radiuses of spherical Pb shield, for both neutron sources. Results: A decreasing flux of gamma-ray was observed when the radius of the spherical Pb shields increased. The value of this reduction was about 94% for 252Cf source when a lead spherical shield of radius 4 cm was used while the reduction was about 50% for 241Am-Be source with the same spherical shield. For a spherical Pb shield of radius 4 cm, reduction of the gamma dose equivalent per source neutron rate was about 8.44×10-17 Sv when the neutron source was 252Cf and about 1.24×10-16 Sv when the neutron source was 241Am-Be. Conclusion: Results show using optimum gamma-ray shield geometry can reduce the patient absorbed dose per incident neutron in a body chemical composition analyzer.}, Keywords = {}, volume = {5}, Number = {1}, pages = {45-51}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-294-en.html}, eprint = {http://ijrr.com/article-1-294-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Kehwar, T.S. and Akber, S.F. and Bhardwaj, A.K. and Dangwal, V.K.}, title = {Accelerated proliferation correction factors in linear-quadratic and multiple-component models}, abstract ={Background: Study in design to incorporate accelerated proliferation correction factors into linearquadratic and multiple-component models. Materials and Methods: Accelerated proliferation rate correction factor has been incorporated into the linearquadratic and the multiple component models by applying accelerated exponential cell growth to explain the tumor cell kinetics and estimates proper treatment results. Biological effectiveness and tumor control probability, in terms of BED (LQ model), BRD (MC model), TCP(LQ model) and TCP(MC model), were computed for three conventional and two accelerated hyperfractionated radiation therapy treatment schedules with using a range of accelerated proliferation rate constants to demonstrate the effect of the proliferation process. Results: The results of the study show that the accelerated proliferation rate reduces the effectiveness of a treatment schedule delivered in a prolonged period of time. Conclusion: Care should be taken in the selection of a treatment protocol for a patient of head and neck cancer with an account of the cell kinetics of the tumor.}, Keywords = {Accelerated proliferation rate, growth fraction, tumor control probability, LQ model, MC model.}, volume = {5}, Number = {2}, pages = {53-61}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-306-en.html}, eprint = {http://ijrr.com/article-1-306-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Fazeli, Gh.R. and Khoei, S. and Nikoofar, A.R. and Goliaei, B.}, title = {Reduced DNA damage in tumor spheroids compared to monolayer cultures exposed to ionizing radiation}, abstract ={Background: Several cell lines when cultured under proper condition can form three dimensional structures called multicellular tumor spheroids. Tumor spheroids are valuable in vitro models for studying physical and biological behavior of real tumors. A number of previous studies using a variety of techniques have shown no relationship between radiosensitivity and DNA strand breaks in monolayer and spheroid model of cell culture. Materials and Methods: In the present study, the radiosensitivity of cells grown as monolayer and spheroid were measured with colony assay and the role of DNA strand breaks in this sensitivity was examined using single cell gel electrophoresis assay also known as Comet assay. Results: In the present experiment, spheroids showed more radioresistance than monolayers as judged by the number of colonies which they produced after radiation. Under the same experimental conditions, less level of DNA damage was detected in spheroids using "comet assay" technique. Conclusion: It was concluded that the loss of radioresistance which was observed in monolayer cultures might have been attributed to the higher level of DNA damage occurred in the cells.}, Keywords = {Multicellular tumor spheroid, DU 145, radiosensitivity, DNA damage, comet assay.}, volume = {5}, Number = {2}, pages = {63-69}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-307-en.html}, eprint = {http://ijrr.com/article-1-307-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Gehlot, P. and Goyal, P.K.}, title = {Rectification of radiation-induced damage in swiss albino mice by aloe vera leaf extracts (AVE)}, abstract ={Background: From the time immemorial man has been exposed to ionizing radiation from the environment in which he lives. Radiation protection concepts and philosophy have been evolving over the past several decades. Materials and Methods: The radioprotective of effect of Aloe vera leaf extract (1000 mg /kg b.wt. orally for 15 consecutive days) has been studied against 6 Gy of gamma radiation in the intestine of Swiss albino mice at various post - irradiation intervals viz. 12 hrs, 24 hrs. and 3, 5, 10, 20 and 30 days. Results: Crypt survival, villus length, apoptic cells, mitotic figures and goblet cells in jejunum were studied after irradiation. Irradiaton produced a significant decrease in crypt survival, mitotic figures and villus length whereas goblet and apoptic cells showed a significant increase from sham irradiated animals. The major changes were observed on day 3 after irradiation. AVE pre-treated irradiated animals resulted in a significant increase in the number of crypt cells, mitotic figures and villus length whereas the counts of apoptic and goblet cells showed a significant decrease from respective control group at all the autopsy intervals. Irradiated animals resulted in the elevation in lipid peroxidation and a reduction in glutathione acitivity. On contrary, AVE treatment before irradiation caused a significant depletion in lipid peroxidation and elevation in glutathione activity. Conclusion: The present study suggests the possible radioprotective ability of Aloe vera leaf extract.}, Keywords = {Aloe vera, Swiss albino mice, LPO, GSH, gamma irradiation.}, volume = {5}, Number = {2}, pages = {71-78}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-308-en.html}, eprint = {http://ijrr.com/article-1-308-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Al-Saeedi, Fatim}, title = {[Methyl-14C]-choline incorporation into nude mice bearing tumor xenografts-correlation with [methyl-3H]-thymidine: A pilot study}, abstract ={Background: Many in vitro studies suggested that choline incorporation into many types of tumors is related to cell proliferation. Whether in vivo choline incorporation is related also to cell proliferation or not was my question. Therefore, the aim of this pilot study was to investigate the relationship of in vivo [methyl- 14C]-choline incorporation and in vivo [methyl-3H]- thymidine incorporation. Materials and Methods: Four female nude mice were inoculated with MCF-7 breast tumor cells. Tumors were allowed to grow to a diameter of 0.5 cm and a diameter of 1 cm. Radioactivity of 370 kBq [methyl-14C]-choline and [methyl-3H]-thymidine each was injected. After 10 min, tumors were harvested and extracted with organic and aqueous solvents. The total [methyl-3H]-thymidine and [methyl-14C]-choline were determined and correlated using Spearman's rank (rs) coefficient at 0.5 cm (n=4) and 1 cm (n=3) tumors. Results: Spearman's rank (rs) correlation coefficient showed high rs=0.8 (p=0.2 n=4) at 0.5 cm tumor compared to low rs=0.5 (p=0.7 n=3) at 1 cm tumor. Conclusion: In this preliminary pilot study, in vivo [methyl-14C]-choline incorporation may correlate with cell proliferation. More number of investigations is recommended.}, Keywords = {Choline, thymidine, tumor, proliferation, MCF-7 cells, nude mice.}, volume = {5}, Number = {2}, pages = {79-83}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-309-en.html}, eprint = {http://ijrr.com/article-1-309-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Yazdani, M. and Mowlavi, A.A.}, title = {Determining TG-43 brachytherapy dosimetry parameters and dose distribution for a 131Cs source model CS-1}, abstract ={Background: Monte Carlo determination of TG-43 brachytherapy dosimetry parameters and dose distribution calculation for 131Cs source model CS-1 are presented in this study. Materials and Methods: The dose distribution was calculated around the 131Cs Model CS-1 located in the center of 30 cm ×30 cm ×30 cm water, and soft tissue phantoms cube using MCNP code by Monte Carlo method. The percentage depth dose (PDD) variation along the different axis, parallel and perpendicular, the source was calculated. Then, the isodose curves for 100%, 75%, 50% and 25% PDD were constructed. Finally, F(r,|θ|) and g(r) dosimetry parameters of TG-43 protocol have been determined. Results: Results obtained show that the Monte Carlo method could only calculate dose deposition in high gradient region, near the source, accurately. The energy cut off was found to be 1 eV and the error in the calculations was less than 2%. Conclusion: The isodose curves of the CS-1 131Cs source were constructed from dose calculation by MCNP code. The calculated dosimetry parameters for the source were in agreement with previously published results.}, Keywords = {131 Cs source, dose distribution, isodose curves, MCNP code.}, volume = {5}, Number = {2}, pages = {85-90}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-310-en.html}, eprint = {http://ijrr.com/article-1-310-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Mesbahi, A. and Naseri, A. R. and Oskoi, GH.}, title = {Experimental evaluation of midline dose calculation methods in In vivo dosimetry using anatomic thorax phantom}, abstract ={Background: In vivo dosimetry is a method for estimation of overall error in the delivered dose to the patients at the end of radiotherapy process. In this research, two methods for target dose calculation were evaluated on midline and central axis of photon beams in in vivo dosimetry of thorax fields. Materials and Methods: Entrance and exit doses for anterior and lateral fields of thorax were measured in thorax phantom using diode dosimeter. Also, the doses of some points on midline and central axis were measured in thorax phantom using ionization chamber. The dose at these points was calculated using entrance and exit doses by geometric and arithmetic mean methods. The calculated doses were compared with measured doses. Results: In all cases, arithmetic mean method showed errors from %8.8 to 19% for points on midline and central axis in comparison to measurements. The range of errors for geometric method was from %1.5 to %8 depending on distance from midline. Conclusion: The results showed that doses of points on midline and central axis can be calculated with acceptable accuracy from entrance and exit doses using geometric mean in thorax fields.}, Keywords = {In vivo dosimetry, midline dose, radiotherapy of thorax, exit dose, entrance dose.}, volume = {5}, Number = {2}, pages = {91-95}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-312-en.html}, eprint = {http://ijrr.com/article-1-312-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Hosseini, S.A.}, title = {Radioactivity monitoring in drinking water of Zahedan, Iran}, abstract ={Background: The present research has focused on the effect of radioactivity on drinking water from five sites in the region of Zahedan city. Materials and Methods: The measurement of water activity in wells, river and spring has been used as a screening method. The determination of gamma emitters was performed by use the application of gamma spectrometry. Results: The values of Radium concentration was between less than 2 mBq/l to 3±0.4 for water wells, 5±0.4 mBq/L for river, and less than 2 mBq/L for spring. Conclusion: All values of activity in the selected water samples were lower than the permissible limit for drinking water consumption. The water was safe for drinking, washing and agricultural use.}, Keywords = {Drinking water, radioactivity, radium isotopes.}, volume = {5}, Number = {2}, pages = {97-100}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-313-en.html}, eprint = {http://ijrr.com/article-1-313-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Tavakoli, M.B. and Shahi, Z.}, title = {Solar ultraviolet radiation on the ground level of Isfahan}, abstract ={Introduction: Ultraviolet (UV) radiation affects human organs such as skin, eyes and immune system, as well as animals and plants. The main natural source of UV radiation is the Sun. To study the effects of solar UV radiation there is a need to quantify variations of solar energy received on the earth surface at different intervals. Materials and Methods: To measure UV radiation a broadband fiber optic UV spectrometer was used. With the spectrometer, the energy received at earth surface was measured from wavelength 100 to 400 nm (the UV spectrum). Measurement duration was from January first to the end of December 2003, and from sunrise to sunset. Results: The received UVC at the ground level was too low to be measured. The measured UVA was between 11 to 21 times higher than UVB energy during the measurement period. The minimum UV received on the ground level was in January and it was 14.5×105 J/m2 while the maximum was in July and it was 80.14×105 J/m2. Total UV radiation received on the ground level was during the year of measurement period 579 ×105 J/m2. Conclusion: The measurement showed that UVC intensity on the earth surface was negligible. As the wavelength increased the receiving UV energy at the ground level also increased. From the results, it has become clear that the main health consequences of solar UV were related to UVA band. As the intensity of the UVR during summer is too high, a method of UV health risk reduction should be devised.}, Keywords = {Ultraviolet radiation, solar UVR, spectrophotometry, skin cancer.}, volume = {5}, Number = {2}, pages = {101-104}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-314-en.html}, eprint = {http://ijrr.com/article-1-314-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {M., Ahaskar and K.V., Sharma and S., Singh and Sisodia, R.}, title = {Post treatment effect of Grewia asiatica against radiation induced biochemical changes in brain of Swiss albino mice}, abstract ={Background: The aim of the present study was to evaluate the radioprotective effect of Grewia asiatica fruit pulp extract (GAE) on Swiss albino mice exposed to gamma radiation. In the present study radioprotective efficacy of Grewia asiatica (rich in anthocyanin, carotenes, vitamin C, etc.) was studied against radiation induced biochemical alterations in mice cerebrum. Materials and Methods: For experimental study, healthy Swiss Albino mice were selected from an inbred colony and divided into four groups. Group I (normal) did not receive any treatment. Group II was orally supplemented (GAE) once daily at the dose of 700 mg/kg.b.wt/day for fifteen consecutive days. Group III (control) received distilled water orally equivalent to GAE for fifteen days than exposed to 5 Gy of gamma radiation. Group IV (IR+Drug) was administered orally (GAE) for 15 consecutive days once daily after exposed to single dose of 5Gy of gamma radiation respectively. Mice were sacrificed at different autopsy intervals viz. 1, 3, 7, 15 and 30 days and brain were removed for various biochemical estimations viz. glutathione (GSH), lipid peroxidation (LPO) and protein. Results: GAE post treatment renders protection against various biochemical changes in mice brain. Radiation induced augmentation in the levels of LPO was significantly ameliorated by GAE post-treatment. Radiation-induced depletion in the level of GSH, protein was checked significantly by GAE administration. Conclusion: These results indicate that Grewia asiatica fruit extract (GAE) is able to protect the brain of Swiss albino mice against radiation induced biochemical alterations.}, Keywords = {Grewia asiatica, antioxidant, lipid peroxidation, protein, radioprotection, reduced glutathione.}, volume = {5}, Number = {3}, pages = {105-112}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-322-en.html}, eprint = {http://ijrr.com/article-1-322-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {HajizadehSaffar, M. and Nekoee, S. and HajizadehSaffar, E.}, title = {A survey of annual effective and genetically significant dose from conventional X-ray examinations in 10 counties in Khorasan province-Iran}, abstract ={Background: A study has been conducted to assess two useful radiation protection indices, the annual per-capita effective dose equivalent (AED) and the genetically significant dose (GSD), from conventional diagnostic radiography in 10 counties with more than 1,886,000 inhabitants in Khorasan province in Iran. Materials and Methods: The health centre authorities of Khorasan province were asked to record data of their patients (sex, age, weight and height) who had undergone radiography during one month starting October 2002, with the radiography specifications (kVp, mAs, FSD, field size) and conditions of the X-ray machines (filtration, model and performance). Based on the gonad absorbed dose level, the radiography data were first divided into 5 groups. Then, the average gonad and effective dose of the radiography groups were estimated using ODS-60 software, and finally, GSD and AED of each county were calculated. Results: Average number of radiography per thousand inhabitant was 34.5 in this study, which varied from 9.4 (Kashmar) to 109.4 (Ferdos). Number of X-ray units per 1000 population was 0.008. The GSD and AED of inhabitants in 10 counties in Khorasan province is 0.012 and 0.014 mGy/y/person respectively. Conclusion: The GSD and AED of 10 counties in Khorasan province were much lower than those in most of other countries, which would have been due to lower number of X-ray units and examinations per 1000 inhabitants. Although this would reduce the risk of radiation absorbed dose from medical diagnostic, but it also showed need to improve and expand the health care facility and services in those cities.}, Keywords = {Annual effective dose, genetically significant dose, conventional diagnostic radiography.}, volume = {5}, Number = {3}, pages = {113-118}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-323-en.html}, eprint = {http://ijrr.com/article-1-323-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Jadidi, M. and Firoozabadi, S.M.P. and Rashidy-Pour, A. and Bolouri, B. and Fathollahi, Y.}, title = {Low-power density of 950 MHz radiation does not affect long-term potentiation in rat dentate gyrus}, abstract ={Introduction: Over the last decade, exposure to non-ionizing electromagnetic waves due to base station antenna has increased. This in vivo study was planned for evaluating the effects of whole-body exposure to 950 MHz field of GSM mobile phone system on rat dentate gyrus long-term potentiation. Materials and Methods: 24 naive male Wistar rats (3 month old, 225|¡|25 g) were randomly divided in the three groups (sham-exposed, GSM and continuous field exposed). The exposure program was planned for 10 sessions at 3 days. Animals were exposed to electromagnetic field for 45 minutes in a circular plastic chamber (mean power density=0.835 mW/cm2). Immediately after end exposure, anesthesia was induced for long term potentiation (LTP) induction. Field potentials were recorded and analyzed using the population spike amplitude and EPSP slope for 60- min. Results: There were no significant differences in population spike amplitude, EPSP slope and EPSP slope maintenance among the three groups. Conclusion: This study provides no evidence indicating that long-term potentiation can be affected by the whole-body exposure to low-power density of 950 MHz field of GSM mobile phone system.}, Keywords = {Electromagnetic field, base station, long-term potentiation, dentate gyrus, rat.}, volume = {5}, Number = {3}, pages = {119-124}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-324-en.html}, eprint = {http://ijrr.com/article-1-324-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Purohit, R.K. and Chakrawarti, A. and Bhartiya, K.M.}, title = {Radiation and cadmium induced biochemical alterations in mouse kidney}, abstract ={Background: In the present investigation radiation and cadmium induced biochemical changes in the kidney of Swiss albino mice have been studied. Materials and Methods: For this purpose, adult male Swiss albino mice (6-8 weeks old) were divided into four groups. Group I (sham-irradiated), Group II (treated with CdCl2 solution 20 ppm), Group III (irradiated with 1.25, 2.5 and 5.0 Gy gamma rays), Group IV (both irradiated with 1.25, 2.5 and 5.0 Gy gamma rays and treated with CdCl2 solution). The animals were autopsied after 1, 2, 4, 7, 14 and 28 days of treatment. The kidney was taken out and different biochemical parameters, such as total proteins, glycogen, cholesterol, acid phosphatase activity, alkaline phosphatase activity, DNA and RNA were estimated. Results: In irradiated animals, the values of total proteins, glycogen, acid phosphatase, alkaline phosphatase activity and RNA increased continuously up to day-7 and decreased thereafter up to day-28. The changes were dose dependent. In CdCl2 treated animals, the values of glycogen and total proteins decreased during the early intervals and increased thereafter whereas the values of acid and alkaline phosphatase activity and RNA increased during early intervals and decreased thereafter. The values of cholesterol and DNA showed decrease in all the experimental groups (except group I) up to day-7 and increase thereafter up to day-28. After combined treatment also, the parameters followed the same pattern of increase and decrease, but the changes were more pronounced indicating their synergistic effect. The biochemical parameters showed highly significant values (P<0.001) as compared to normal ones. Conclusion: These results indicate that combined treatment of cadmium and gamma radiations causes synergistic or additive effect.}, Keywords = {Radiation, cadmium, kidney, mice.}, volume = {5}, Number = {3}, pages = {125-130}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-325-en.html}, eprint = {http://ijrr.com/article-1-325-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Foroutan, H. and hodabakhsh, M. and Rabbani, M.}, title = {Investigation of synthesis of PVP hydrogel by irradiation}, abstract ={Background: A dressing often covers the wound to accelerate its healing. Hydrocolloid-type dressing to give better conditions for healing has been developed consisting of gelatin, pectin, water and hydrophilic polymer which promote healing. In recent years, much attention has been focused on the research and development of polymer hydrogels as biomaterials, such as contact lenses, wound dressing and drugdelivery systems. Materials and Methods: Hydrogels, as wound dressing were prepared with composite poly (N-vinyl-2-pyrolidone) (PVP) with several additives such as agar and polyethylenglycol (PEG) and by electron-beam. Electron beam was applied as a tool for initiation of crosslinking and sterilization of these materials. The effects of irradiation dose at the range of 10-40 KGy and various concentration of components on the characterizes of hydrogel such as gel content, degree of swelling (DS), equilibrium water content (EWC) and dehydration properties, transparency and microbial test were investigated. Results: After irradiation, the achieved gel content of hydrogels was obtained higher than 25%. Gels' degree of swelling with different concentrations was changed from 35 to 20 at the range of irradiation dose of 10-40 KGy. Also, at the same range of irradiation and concentration, EWC of gels was found to be 98 to 94 %. The dehydration results did not show variation with the tested parameters. Conclusion: Results showed that hydrogels membrane with composition PVP (10% w/w), agar and PEG (1-3%w/w) at the dose of 25 KGy had the amount of gel content 80-85%. Their DS and EWC were respectively obtained 30% and 96.5%. They were elastic, transparent, flexible, sterile and impermeable for bacteria. They absorbed a high capacity of water, attached to healthy skin, and they were easy to remove. It was concluded that the network was solely composed of crosslinked PVP plasticized by other compounds.}, Keywords = {Hydrogel, biomaterial, radiation polymerization, electron beams, wound dressing.}, volume = {5}, Number = {3}, pages = {131-136}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-326-en.html}, eprint = {http://ijrr.com/article-1-326-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Miri-Hakimabad, H. and Vejdani-Noghreiyan, A. and Panjeh, H.}, title = {The safety of a landmine detection system using graphite and polyethylene moderator}, abstract ={Background: Several landmine detection methods, based on nuclear techniques, have been suggested up to now. Neutron-induced gamma emission, neutron and gamma attenuation, and fast neutron backscattering are the nuclear methods used for landmine detection. In this paper an optimized (safe and effective) moderating structure using an 241Am-Be neutron source for detecting landmines has been investigated by experiment and MCNP simulation. Materials and Methods: The experimental set up was composed of a lead (Pb) cylindrical shell enclosing the neutron source, embedded in a fixed size high-density polyethylene (HDPe) cylinder with the variable thickness of the upper and lower moderator/reflector. Some experimental groups were used to measure several moderator configurations' responses by replacing a thermal neutron detector with the mine and counting the neutron capture events. Results: the total experimental results led to the introduction of optimum moderator geometry for landmine detection. A safe landmine detection system was obtained which enabled the operator to use it for 950 h/year, regarding the dose limit recommended by ICRP. Conclusion: The novel method for optimization applied in this work is more applicable than the usual approach that is based on measuring the prompt gamma rays emitted by the landmine. Results showed that the method can be optimized in short time, without the usual difficulties of the other methods.}, Keywords = {Am-Be neutron source, landmine detection, optimization, BF3 detector, HDPe, graphite.}, volume = {5}, Number = {3}, pages = {137-142}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-327-en.html}, eprint = {http://ijrr.com/article-1-327-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Mortazavi, S.M.J. and Mosleh-Shirazi, M.A. and Maheri, M.R. and Yousefnia, H. and Zolghadri, S. and Haji-pour, A.}, title = {Production of an economic high-density concrete for shielding megavoltage radiotherapy rooms and nuclear reactors}, abstract ={Background: In megavoltage radiotherapy rooms, ordinary concrete is usually used due to its low construction costs, although higher density concrete are sometimes used, as well. The use of high-density concrete decreases the required thickness of the concrete barrier hence, its disadvantage is its high cost. In a nuclear reactor, neutron radiation is the most difficult to shield. A method for production of economic high-density concrete with appropriate engineering properties would be very useful. Materials and Methods: Galena (PbS) mineral was used to produce of a high-density concrete. Galena can be found in many parts of Iran. Two types of concrete mixes were produced. The water-to-concrete (w/c) ratios of the reference and galena concrete mixes were 0.53 and 0.25, respectively. To measure the gamma radiation attenuation of Galena concrete samples, they were exposed to a narrow beam of gamma rays emitted from a cobalt-60 therapy unit. Results: The Galena mineral used in this study had a density of 7400 kg/m3. The concrete samples had a density of 4800 kg/m3. The measured half value layer thickness of the Galena concrete samples for cobalt- 60 gamma rays was much less than that of ordinary concrete (2.6 cm compared to 6.0 cm). Furthermore, the galena concrete samples had significantly higher compressive strength (500 kg/cm2 compared to 300 kg/cm2). Conclusion: The Galena concrete samples made in our laboratories had showed good shielding/engineering properties in comparison with all samples made by using high-density materials other than depleted uranium. Based on the preliminary results, Galena concrete is maybe a suitable option where high-density concrete is required in megavoltage radiotherapy rooms as well as nuclear reactors.}, Keywords = {High-density concrete, galena, shielding, megavoltage radiotherapy.}, volume = {5}, Number = {3}, pages = {143-146}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-328-en.html}, eprint = {http://ijrr.com/article-1-328-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Tavakoli, M.B. and Shahbazi-Gahrouei, D. and Hosseinpour, M.}, title = {Dosimetric characteristics of 137Cs sources used in after loading Selectron system by Monte Carlo method}, abstract ={Background: For an effective treatment planning in brachytherapy, it is necessary to know the accurate source dosimetric information such as air kerma strength, exposure rate constant, dose rate constant and redial dose distribution. The usual method to determine these factors is thermo luminescent dosimeter (TLD) dosimetry. Nowadays, another more accurate method is known to be the Monte Carlo simulation, and it is widely used in determining of brachytherapy sources dosimetric factors. The aim of the present study has been determine to dose distribution of 137Cs sources configuration used in interacavitary low dose rate (LDR) Selectron brachytherapy by Monte Carlo simulation method. Materials and Methods: Simulation has been performed for 137Cs stainless-steel encapsulated source in 2.5 mm in diameter of Selectron system. Six different combinations of 137Cs sources were simulated and each combination was put into different applicator. The Monte Carlo MCNP4C code was used for simulation. The number of history was taken 1 million for the calculation of air kerma strength and exposure rate constant and 0.1 million for calculating dose rate constant and redials dose distribution. Results: Maximum air kerma strength was obtained for the combination with fourteen active sources and found to be 919.3 |µ|Gym2h-1 while its minimum value was 133.9 µ|Gym2h-1 for the case with two active sources. Maximum and minimum dose rate constant of 4.3 cGyh-1mCi-1 and 2.1 cGyh-1mCi-1 were obtained for the combination with eight and fourteen active sources, respectively. Conclusion: The results indicated that the Monte Carlo simulation method may be useful to determine dosimetric characteristics of brachytherapy sources.}, Keywords = {137Cs, brachytherapy, redial dose, dose rate constant, Monte Carlo simulation.}, volume = {5}, Number = {3}, pages = {147-151}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-329-en.html}, eprint = {http://ijrr.com/article-1-329-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2007} } @article{ author = {Awan, S.B. and Hussain, M. and Dini, S.A. and Meigooni, A.S.}, title = {Historical review of interstitial prostate brachytherapy}, abstract ={In the recent years, interstitial brachytherapy implantation has become the treatment of choice for early stage prostate cancer patients. Treatment of prostate cancer with radiation is traced back to 1909. Originally this treatment modality was very crude and could not gain much popularity till 1982. Advancements in radioactive source designs, introduction of new low energy radioactive sources, and new imaging modalities made this treatment modality a treatment of choice for early stage prostate cancer patients. Popularity of this modality is due to the fact that five-and ten-year disease control rates of brachytherapy are equal to those of the surgical, whereas, the toxicity and side-effects are perceived to be lower. This manuscript presents historical review of interstitial brachytherapy, innovations in radioactive source designs, dosimetry and dose calculations.}, Keywords = {Interstitial brachytherapy, advancements, Ra-226, Au-198, I-125, Pd-103, Cs-131.}, volume = {5}, Number = {4}, pages = {153-168}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-345-en.html}, eprint = {http://ijrr.com/article-1-345-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Anjum, M.N. and Qadir, A. and Afzal, M.}, title = {Dosimetric evaluation of a treatment planning system using pencil beam convolution algorithm for enhanced dynamic wedges with symmetric and asymmetric fields}, abstract ={Background: The dosimetric performance of Eclipse 6.5 three dimensional treatment planning system (3DTPS) is evaluated by comparing the calculated and measured dose in two dimensions following the guide lines of American Association for Physicists in Medicine Task Group 53. Materials and Methods: The calculations were performed by the 3DTPS for symmetric as well as asymmetric fields for standard source to surface distance (SSD) at dmax, 5, 10 and 20cm depths in water phantom using 45° and 60° enhanced dynamic wedges (EDWs) in a field of 15 cm×15 cm size for 6 MV photon beams. Measurements were carried out for 6 MV photon beams produced by a linear accelerator, Clinac EX - 2100, equipped with EDWs using 0.125cc volume PTW ionization chamber and PTW UNIDOS electrometer for beam axis and two off axis points. Results: The deviations between the calculated dose (Dcalc) and the measured dose (Dmeas) at toe, centre and heel at different depths for symmetric as well as asymmetric fields for both the wedge angles is less than 2% at all the points and in all geometries. For 45° EDW the deviation was maximum at 20 cm depth and in asymmetric geometry. For 60° EDW the deviation was maximum at 20 cm depth but in symmetric geometry. Conclusion: The results indicate that the accuracy of Eclipse 6.5 (version 7.3.10) three dimensional treatment planning system used with the EDWs in symmetric as well asymmetric fields is adequate in clinical applications under the studied experimental conditio}, Keywords = {Enhanced dynamic wedge, dose distribution comparison, asymmetric fields, treatment planning system, calculation algorithms.}, volume = {5}, Number = {4}, pages = {169-174}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-346-en.html}, eprint = {http://ijrr.com/article-1-346-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Mohagheghi, F. and Mohammadi, M.}, title = {Innovation of a method to decrease interruption time during treatment of pelvic area carcinomas}, abstract ={Background: The presence of small intestine in the radiation field during pelvic cancers treatment causes an interruption in radiotherapy. A non-invasive method was developed to exclude small intestine during conventional radiotherapy. Materials and Methods: The incidence of the radiation therapy interruption is highly dependent upon the area of the small intestine included in the portals and its absorbed dose. In order to investigate the radiation therapy interruption and the resulting elongation of the total treatment time, 35 patients suffering from pelvic cancers were selected and randomly assigned to control and study groups. All the patients were treated in prone position. In the 18 patients in the study group, a commercially available water bag was inserted between patient abdomen and treatment couch. Other 17 patients in the control group underwent similar therapy without water bag. Results: The total treatment time was shown to be 1.52 days shorter in the study group with a statistically significant difference (p<0.003). Conclusion: Due to the lack of the early morbidities during radiotherapy, it is concluded that the current method helps to optimize total treatment time by preventing interruption of radiation therapy.}, Keywords = {Pelvic cancers, small intestine, acute morbidity, chronic morbidity, treatment delay.}, volume = {5}, Number = {4}, pages = {175-180}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-347-en.html}, eprint = {http://ijrr.com/article-1-347-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Mesbahi, A.}, title = {Radial dose functions of GZP6 intracavitary brachytherapy 60Co sources: treatment planning system versus Monte Carlo calculations}, abstract ={Background: The Monte Carlo (MC) method is not only used for dose calculations around brachytherapy sources but also for benchmarking treatment planning systems (TPS) calculations. Materials and Methods: Three 60Co sources of GZP6 brachytherapy unit were simulated using MCNP4C MC Code. The radial dose functions were calculated by MC method and GZP6 TPS and were compared. Results: There was a good agreement between MC and TPS calculations for all sources. Discrepancies up to 10% were observed for points close to the sources, but for those farther than 7mm from source center, differences were less than 2% for all sources. Conclusion: Our results showed that GZP6 TPS calculations can accurately be used for dose calculations in brachytherapy treatments for points farther than 7mm from the source center.}, Keywords = {Brachytherapy, high dose rate (HDR), 60Co, Monte Carlo.}, volume = {5}, Number = {4}, pages = {181-186}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-348-en.html}, eprint = {http://ijrr.com/article-1-348-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Mozdarani, H. and Salimi, M. and Froughizadeh, M.}, title = {Effect of cimetidine and famotidine on survival of lethally gamma irradiated mice}, abstract ={Background: Currently available radioprotectors are poorly tolerated in man and the general use of aminothiols is compromised by their side effects. This study was carried out to test and compare the radioprotective potential of cimetidine and famotidine against lethally gamma irradiated NMRI mice. Materials and Methods: Adult male NMRI mice in groups of 10 were exposed to various doses of gamma rays at a dose rate of 93.3 cGy generated from a Co- 60 source. Mortality was examined daily for 30 days after irradiation. Various doses of gamma rays were used to calculate LD50/30. Different doses of cimetidine and famotidine were used in combination with 8 Gy gamma rays to find out the optimum protecting concentration of either drug. Finally the optimum protecting concentration of either drug was used in combination with various doses of gamma rays. Each experiment was repeated for three times. Results: Results show that mean LD50/30 for radiation alone was found to be 723.7 cGy. When using different doses of cimetidine in combination with 801 cGy gamma rays, the dose of 15 mg/kg cimetidine produced optimum protection, while optimum dose of famotidine was found to be 10 mg/kg. However, LD50/30 obtained with optimum dose of either cimetidine or famotidine led to a DRF of 1.11 and 1.05 respectively. Conclusion: Cimetidine compared to famotidine was found to be more protective against mortality induced by radiation in mice. This effect of cimetidine might be due to its immunomodulatory role and thus protecting bone marrow and lymphoid tissue injuries following whole body gamma irradiation.}, Keywords = {Radiation lethality, radioprotection, cimetidine, famotidine, LD50/30, DRF.}, volume = {5}, Number = {4}, pages = {187-194}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-349-en.html}, eprint = {http://ijrr.com/article-1-349-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Manigandan, P.K. and Manikandan, N.M.}, title = {Bio-indicators in the tropical forest of western Ghats environment}, abstract ={Introduction: Investigation on the natural radionuclides 238U, 232Th, 40K and natural fallout radionuclide 210Po in the prominent plants species of Western Ghats tropical forest near Kotagiri have been carried out as a part of baseline background radiation studies in the forest environment. Materials and Methods: The prominent plants species of the region Evodia roxburghiana and Eleaocarpus oblangus were chosen and concentrations of 238U, 232Th, 40K and 210Po were measured by employing gamma ray spectrometer and alpha counter. Results: The radioactivity concentrations in plants and soils reflect the impact of the existence of igneous nature of rock in the area of study. Concentration ratios (CR) of these radionuclides, between plants and underlying soil, have been studied and results shows that the concentration ratios (CR) seem to be depend on radionuclides in soil. Conclusion: From careful analysis of the results, these Plants could be used as an indicator to monitor these radionuclides.}, Keywords = {Primordial radionuclides, Western Ghats, monazite, igneous rock, CR -concentration ratio.}, volume = {5}, Number = {4}, pages = {195-202}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-350-en.html}, eprint = {http://ijrr.com/article-1-350-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Ajayi, I.R.}, title = {An evaluation of the equivalent dose due to natural radioactivity in the soil around the consolidated Tin mine in Baukuru-Jos, plateau state of Nigeria}, abstract ={Background: The equivalent dose in the human body due to the natural gamma-emitting radionucides (238U, 232Th and 40K) in the surface soil surrounding the Consolidated Tin mine site in Bukuru-Jos, Nigeria has been determined in this study. Materials and Methods: Measurements of the soil natural radioactivity were made using a multi-channel pulseheight analyzer (Canberra Series 10 plus) coupled to a 76 mm×76 mm Nal (Tl) scintillation detector. Results: The mean concentrations obtained for each of the radionuclides is 35.4±17.6 Bq/kg for 40K 776.0± 158.0 Bq/kg for 238U and 2.72±0.58 kBq/kg for 232Th. The mean absorbed dose rate due to natural radioactivity calculated at a height of 1.0 m above the ground is 2.16 µGy/hr which converts to an equivalent dose of 3.0 mSv/y. Conclusion: The results obtained in this study are far above the world average equivalent dose of 0.41 mSv/y but lower than the annual limit of 20 mSv/y for radiation workers but still represents a health risk to workers on the site.}, Keywords = {Equivalent dose, natural radioactivity, gamma ray,scintillation detector, soil, absorbed dose.}, volume = {5}, Number = {4}, pages = {203-206}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-351-en.html}, eprint = {http://ijrr.com/article-1-351-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} } @article{ author = {Kakavand, T. and Sadeghi, M. and KamaliMoghaddam, K. and ShokriBonab, S. and Fateh, B.}, title = {Computer simulation techniques to design Xenon-124 solid target for iodine-123 production}, abstract ={Background: Iodine-123 (123I) is regarded as one of the best radionuclides for in vivo medical studies using single-photon emission computed tomography (SPECT) due to its suitable physical property. Materials and Methods: To design a new system in order to replace cryogenically solidified xenon target by the gas one, some necessary calculations are needed to be done such as finding the excitation functions variation of the production reactions, thick target yield of 123I production, etc. The computer codes Alice91 and SRIM have been used as a calculation tools. Results: According to the suggested design, a conical shaped irradiation vessel made of copper with thickness of 1mm, outlet diameter of 1 cm, 5 cm length and 12° angle at summit can be fixed inside a liquid nitrogen housing chamber. The 124Xe gas was sent to the inside of this very cold conical trap and eventually deposited on its surface in solid form. Calculation showed that during bombardment with 17- 28 MeV proton energy, the thickness of solidified xenon layer remained about 0.28 mm. Conclusion: The production yield of 123I can be predicted to be around 150 mCi/µAh.}, Keywords = {Cyclotron Accelerator, Iodine-123, Xenon-124 gas, Radiopharmaceutical, Alice91 code, SRIM code.}, volume = {5}, Number = {4}, pages = {207-212}, publisher = {Dr. Hossein Mozdarani}, title_fa = {}, abstract_fa ={}, keywords_fa = {}, url = {http://ijrr.com/article-1-352-en.html}, eprint = {http://ijrr.com/article-1-352-en.pdf}, journal = {International Journal of Radiation Research}, issn = {2322-3243}, eissn = {2345-4229}, year = {2008} }