In cooperation with the Iranian Nuclear Society
Volume & Issue: Volume 31, Issue 1 - Serial Number 51, June 2010, Pages 1-82 

Experimental Study of Neutron Emission Characteristics in SBUPF1 Plasma Focus Device

Pages 1-8

B Shirani; F Abbasi Davani

Abstract In this work, neutron production of SBUPF1 (a 2.5 kJ Mather type plasma focus device) at various pressures of deuterium and two different anode lengths (12 cm, 18 cm) were studied. Three silver activation counters were used at three different angels (0º, 45º and 90º) in order to determine the angular distribution of neutrons. The neutron and hard x-ray pulses were registered by a ø5"×5" plastic scintillator. These pulses were further used to determine the average energy of the detected neutrons. Experiments showed that for the 18cm anode at the optimum gas pressure, the neutron generation has decreased while the neutron yield at this pressure has increased. Under these conditions, the optimum pressure is 6 mbar, the neutron yield at the optimum pressure is about 6.4×107 per pulse, and the average energy of neutrons is 2.24 MeV.

Preparation of [61Cu]Bleomycin Complex as a Potenlial PET Radiopharmaceutical and it’s Biological Evaluation in Normal and Tumor-Bearing Rodents

Pages 9-17

A.R Jalilian; H Zandi; M Akhlaghi; M Kamali Dehghan; F Bolourinovin; S Moradkhani; A Majdabadi

Abstract [61Cu]Bleomycin ([61Cu]BLM) was prepared using [61Cu]CuCl2 produced via natZn(p,x)61Cu (180μA proton irradiation, 22MeV, 3.2h), purified by ion chromatography method. [61Cu]BLM was prepared at optimized conditions (room temperature, 45 min, 0.1 mg bleomycin for 2-10mCi 61CuCl2) with radiochemical purity over 98% determined by HPLC and RTLC. [61Cu]BLM was administered into the normal and tumor bearing rodents up to 210 minutes followed by biodistribution and co incidence imaging studies. A significant tumor/non tumor accumulation was observed either by animal sacrification or imaging method. [61Cu]BLM can be a potential PET radiotracer for tumor imaging.

Heavy Metal Removal from Synthetics Wastes by Natural and Acid-Activated Bentonites

Pages 18-27

S.H Jazayeri; M Hayati Ashtiani; S.N Ashrafizadeh; M Ghannadi Maragheh; A Nozad Golikand

Abstract This paper examines heavy metals removal from synthetics wastes by the use of natural and sulfuric acid-activated bentonite so that a cheap adsorbent can be attained for removing these metals from the wastes. Bentonite is a 2:1 layer aluminnisilicate whose dominant mineral is montmorillonite which is a nano-structure and nanoporous material. Montmorillonite affects all the properties of bentonite. In the next step, the effect of acid activation on the adsorption of both of lead (Pb) and thallium (Tl) is studied. In this research, after the mineralogical and chemical composition analyses by X-ray diffraction and fluorescence (XRD and XRF) methods, granulometric analysis is carried out on five samples namely, S2-RAW, S3-RAW, ES3-RAW, G1-RAW and GH1-RAW to remove the heavy metals such as Cr, Co, Cu, Fe, Pb, Tl, Ni, and Zn accompanying atomic absorption spectroscopy (AAS). Then, the effect of four factors including concentration, liquid to solid ratio (L/S), time, and activation temperature in acid activation process were studied. This process is done by a mineral acid, sulfuric acid, to promote the adsorbability of lead and thallium in both natural and activated types of ES3-RAW and GH1-RAW. In all case, due to the presence of dominant mineral of nano-montmorillonite and its unique structure, montmorillonite has a higher adsorbability in comparison with that of the other clay minerals.

The Effect of Homogenization Procedure on Properties and Microstructure of High Content Lead Glasses

Pages 28-33

Z Hamnabard; s Kakooei; R Rahimi

Abstract Radiation shielding lead glasses can be used in any facility, which requires protection from radiation, for example medical centers, industrial and nuclear sites. Usually, for improvement of optical properties and homogeneity control of these glasses, homogenization process in different ways is applied. One of the important methods, which is also industrially practical for other glass systems, named fritting, is the process of melting and quenching of molten materials to form small glass particles. In the current work, the effect of homogenization on the thermal and physical properties of lead glasses is investigated. In this way, a composition of lead glass was selected. Then fritting procedure applied six times for this composition and the effect of fritting on thermal, physical, properties and homogeneity of glass were discussed. Finally, microstructural analyses of glass specimens were carried out. The results showed that the increase of the fritting period has an unwanted influence on different properties of the glass samples and this process can be used in joint with considering the other effective parameters.

Potential Map Ping and Regional Geochemical Exploration of Uranium by Using Tracers in Esfordi 1:100,000 Sheet

Pages 34-41

Y Ghanbari; S Saen; A memar

Abstract According to Atomic Energy Organization of Iran (AEOI) Uranium exploration program in Central Iran, Esfordi 1:100,000 sheet which is located in Yazd province, between Bafq & Behabad cities was prospected. The analysis result of the stream sediment samples which were collected by the Geography Society of Iran (GSI) have been used for radioactive resources of this area. Due to lacking of uranium, thorium and Rare Earth Elements (REE) analysis data, the uranium tracers have been used. The data processing, i.e. normalization, univariate and multivariate analysis were studied and ultimately, anomalies maps were prepared. Three uranium potential areas were introduced. These areas include marl and conglomerate sequence in North-west of region, south of Zarigan granite and sandstone sequence with aplites between Esfordi mine and Kooshk mine. Thus, Esfordi sheet is important as a sediment hosted uranium deposit.

Adsorption Properties of Amidoxime Resins for Separation of Uranium (VI) from Aqueous Solutions

Pages 42-47

A Nilchi; R Rafiee; A.A Babalou; S Rasouli Garmarodi

Abstract In this study, the acrylonitrile (AN)-divinylbenzene (DVB)-methylacrylate (MA) resin was synthesized via suspension polymerization in the presence of toluene as a diluent, and benzoylperoxide (BPO) as an initiator. The effect of MA, toluene and alkaline treatment on the exchange capacity of the resin were investigated. The results showed that the anion exchange capacity decreases with an increase of the amount of MA, while alkaline treatment has no significant effect. Also, the cation exchange capacity increases with an increase in the amount of hydrophilic agent and reaches a maximum. The sorption equilibrium was achieved relatively fast within 40 minutes. The adsorption of uranium was directly depends on the pH value. Finally, the alkaline treatment enhances the potential for the much faster adsorption and the chelating resin provides a more favourable pore structure for the rapid diffusion of the ions.

Pathological and Molecular Identification of Fusarium Solani F.Sp. Phaseoli Isolates and Determination of Suitable Gamma ray Dose Rate for Mutation Induction

Pages 48-51

H Ahari Mostafavi; N Safie; H Fathollahi; M Babaie; H.R Dorri; M.R Lak

Abstract During 1384-1385, the plants showing root and crown rot were collected from 48 bean fields in the Khuzestan and Markazi provinces. Twenty isolates were identified as Fusarium solani based on morphological characteristics. The pathogenicity tests confirmed four isolates as Fusarium solani
f.sp. phaseoli. By using specific primers for this specific form, three isolates showed concordant results with pathogenicity tests. As a result three isolates morphologically and molecularly identified as F.solani f.sp. phaseoli. In order to induce mutation, conidia scraped from F.solani f.sp. phaseoli cultures, were counted, diluted and then plated on water agar. The plates containing conidia were irradiated in a
60Co-gamma cell (with activity of 2500 curi and 0.38 gray per second dose rates) in doses 0, 60, 90, 120, 150, 180 Gy. After 18 hours, the percentage germination of spores were scored. The comparison of percentage germination and vegetative growth in different dose rates showed that spore mutagenesis can be expected in 120-180 Gy.

The Effects of Different Uranium Concentrations on Soil Microbial Populations and Enzymatic Activities

Pages 52-57

S Bagherifam; A Lakziyan; S.J Ahmadi; A Fotovvat; M.F Rahimi

Abstract Uranium is an ubiquitous constituent of natural environment with an average concentration of 4mg/kg in earth crust. However, in local areas it may exceed the normal concentration due to human activities resulting in radionuclide contamination in groundwater and surface soil. The effect of six levels of uranium concentration (0, 50, 100, 250, 500 and 1000mg kg-1) on soil phosphatase activities and microbial populations were studied in a completely randomized design as a factorial experiment with three replications. The results showed a significant decrease in phosphatase activity. The result of the experiment suggests that soil microbial populations (bacteria, funji and actinomysetes) decrease by increasing the uranium levels in the soil. Therefore, assessment of soil enzymatic activities and microbial populations can be helpful as a useful index for a better management of uranium and radioactive contaminated soils.

Production and Evaluation of 186Re Radionuclide in the Tehran Research Reactor for Therapeutic Applications

Pages 58-62

Sh Sheibani; H Pourbeigi; Y.H Tavakoli; M Keyvani

Abstract In this work, the production of 186Re by 185Re (n,γ) 186Re reaction in the Tehran Research Reactor (T.R.R) is investigated. The activity of 186Re was measured after a cooling time of 4 days, using a liquid beta scintillation system and a dose calibrator. Also, activity of the samples were calculated using fluxes determined by Monte Carlo simulation of the reactor core. The calculated and measured values for the activity of irradiated samples are comparable in the range of ±18% and the irradiation correction factors are 1.135 and 0.820 for natural rhenium (thermal neutron flux of 6.5×1013 cm-2 s-1)and rhenium samples with high the isotope abundance of 185Re (thermal neutron flux of 1.18×1013 cm-2 s-1), respectively. The results have shown that 186Re samples (in the form of perrhenate) can be achieved with 96.5% radiochemical purity and 99% radionuclidic purity. The products with the high specific activity of about 300mCi/mg for therapeutical aplications can be achieved in T.R.R. using rhenium sample target with a high abundance from rhenium-185 target; and for the medium with the mean specific activity, natural rhenium can be used.

Study of Gaseous Pollutants Purification and Filtration System of Uranium Conversion Facility (UCF)

Pages 63-69

A Sadighzade; M Rostami; S Sana

Abstract Gaseous pollutants purification and filtration system of Uranium Conversion Facility includes four Foam Scrubbers and four groups of 24 frame filters to remove dangerous gases and particles from polluted air. In this paper, the purification processes of the dangerous gases in foam towers and removal of the particles in filters are presented. The gas pollution of this facility includes dangerous chemical and radioactive compounds; as a result the high efficiency can be one of the main properties of this purification system. For achieving this goal, theoretical and experimental studies are made to select filter frame media. Our theoretical studies show that the characteristics of the best filter media are: upper thickness, high porosity and formed by fine fibers. The experimental studies to select suitable media concerning efficiency, pressure drop, chemical and mechanical resistance are done in 30 filter media. The efficiency of chosen media is determined of about 99.7% by the experiment. In addition, a semi industrial sample of foam scrubber system was designed and built. The absorption efficiency of the system for acidic gas, the same as in UCF, was measured to be about 97%. Considering these results and prevailing the standards used in UCF and also the level of air pollution in workshops, the air pollution level in the stack outlet must not surpass the authorized amount.  

Investigation of Percentage Depth Dose (PDD) and Dose Rate Dependence of PAGAT Polymer Gel Dosimeter for Photon Beams Using MRI Technique

Pages 70-76

B Azadbakht; K Hadad; M.H Zahmatkesh

Abstract In this work, the investigation of the normoxic PAGAT polymer-gel dosimeter percentage depth dose (PDD) and it’s dose rate dependence has been made. Using MRI, the formulation to give the maximum change in the transverse relaxation rate R2 was determined to be 4.5% N,N'-methylen-bis-acrylamide©(bis), 4.5% acrylamid (AA), 5% gelatine, 5mM tetrakis (hydroxymethyl) phosphonium chloride (THPC), 0.01 mM hydroquinone (HQ) and 86% HPLC(Water). Irradiation of vials was performed using photon beams of Co-60 therapy unit and an Electa linear accelerator. Gel dosimeters were imaged in a Siemens Symphony 1.5 Tesla clinical MRI scanner using a head coil. Post-manufacture irradiation and post imaging times were both selected to be 1 day. For determing the percentage depth dose of the PAGAT gel it was found that at the depth of 21cm, the percentage depth dose for 1.25 MeV γ-ray photons of 60Co and for 4,6 and 18 MV x-ray photons of Electa linear accelerator, are 48%, 52%, 57.3% and 59.73%, respectively. Thus, in the case of the higher energy photon beams, a higher dose can be delivered to deep-seated tumors. The dose rate dependence of PDD was studied for 6 MV x-ray photons with the use of dose rates of 80, 160, 240, 320, 400 and 480cGy/min. No trend in polymer-gel dosimeter 1/T2 dependence was found on the mean dose rate and energy for the photon beams.

Preparation of CaF2 Thermoluminescence Dosimeter and Investigating of the Influence of Dy Impurity in it’s Dosimetric Properties

Pages 77-82

M Gholampoor; J Gheisari; Gh Mirjalili; M.A Shafaie; l shekari; A.R Moini; A Shahvar

Abstract In this study, CaF2 pellet samples were prepared and its thermoluminescence (TL) properties were investigated after gamma irradiation. The TL glow curve of the CaF2 pellet has four peaks at around 135, 170, 260 and 370ºC for the heating rate of 10ºC/S. The main peak occurs at 260ºC. The sensivity of CaF2 and Dy doped CaF2 were examined. The observed TL sensivity of the prepared CaF2 pellet is abut five times than that of TLD-100. The sensivity of the Dy doped CaF2 is approximately 18 times higher than that of TLD-100. The fading is approximately 13% in one day, 36% in two days and 50% in 500 hours. These examinations repeated for 10 times and all the results were found to be consistant. These properties make the CaF2 pellets a useful can dilate for γ-ray irradiation dosimetry applications.