جمال امیری

We measured radiation emission from the patients undergoing myocardial perfusion scan after leaving nuclear medicine department to demonstrate how much radiation hospital staff or patients’ companions, in the vicinity of the patients would receive. We also evaluated the relationship of age, sex, and body mass index with the emitted radiation rate.

In this study 60 patients (41 females and 19 males) after undergoing 99mTc-sestamibi myocardial perfusion scan with a dose of 925±185 MBq, were selected randomly. The equivalent dose rate at distances of 0.25 m, 1 m and 2 m from the patients were measured by a survey meter before leaving nuclear medicine department and after 12 & 24 hours. Data were analyzed by T-test, Pearson correlation coefficient and ANOVA.

The mean equivalent dose rates in unit of microsievert per hour at distances of 0.25 m, 1 m and 2 m from the patients were (120.6 ± 24.1, 19.4 ± 3.8, 8.4 ± 1.3) at leaving time, (29.1 ± 8.7, 5.3 ± 1.2, 2.1 ± 0.8) after 12 hours and (4.3 ± 1.5, 0.8 ± 0.6, 0.3 ± 0.1) after 24 hours, respectively. The mean equivalent dose rate showed no relationship with gender and age, but it was inversely correlated with body mass index (P-value <0.05) after 24 hours.

People would receive reasonably low radiation if they keep a distance of at least 1 meter from the patients or stay only for a few minutes in the vicinity of the patients. After 24 hours, equivalent dose rate was inversely correlated with body mass index.

Using ionizing radiation in diagnosis and treatment is of great importance. As early diagnosis in some diseases only can be done by using radiation, in treatment phase, radiotherapy is also the main center for healing patients with cancer. Today, one of occupational hazards is ionizing radiation which can cause serious and irreparable damages in radiation workers. This study aimed to count blood cells and evaluate liver enzymes and thyroid-stimulating hormone (TSH) in radiation workers in hospitals in Kurdistan Province, Iran.
In this case-control study, blood cells, liver enzymes, and TSH levels were compared in 142 radiation staff (cases) and also 142 workers in other sections of hospitals. Matching was done for confounding factors. The statistical analysis was performed using SPSS software at the significance level of P Findings: Mean number of white blood cells and the level of serum alanine aminotransferase (ALT) enzyme in radiation staff were significantly different from that of the control group. But no significant difference was observed between other parameters.
It seems that working in radiation wards can change some blood factors but can not predict the recieved dose. In order to increase the safety of radiation workers in radiation wards, monitoring of these individuals should be done annually using cytogenetic methods.

Introduction and Aim: the interaction of neutrons with light elements is used in neutron activation (NAA), neutron therapy (BNCT) and etc. in order to use the neutrons optimally, their energy spectrum has to be tailored to their practical purposes. When doing neutron therapy, the light elements which are located in the treatment site are activated and the instantaneous gamma ray has a specific value for each element using which the quantity of the lement is measured in the site. In this study, the effect of energy spectrum on the activation of neutron which is used in neutron therapy was studied.
Material and MCNP softwere was used to simulate. First, all if the neutron spectra, such as neutron generator (MeV14) and the spectrum of the reactor and isotope sources were evaluated. The resulted spectrums of these sources were simulated by MCNP software. Considering the ability of this software in the transport of nwutrons and ogher particles and gamma flux measurements derived from them, the most optimal neutron energy spectrum of gamma for identifying htdrogen, carbon, and oxyeen elements was introduced.
Findings: the best spectrum of energy in order to identify the light elements in the energy range of BNCT (KeV10-1) is a spectrum of energy which has thermal neutrons (similar to Maxwell spectrum).Hydrogen has a good cross section for interaction with thermal neutrons. Oxygen and carbon has a good cross section with swift neutrons. By using neutron source MeV14 the neutron generator, hydrogen energe peak is less than when the source energy spectrum is similar to Maxwell and has higher oxyen and carbon peak.
Therfore, there is better output for therapeutic purposes, detection and analysis of light lelments like Maxwell (reactor or isotope sources). However, if the ratio of oxygen to carbon is measured and the mono energy sourse MeV14 be used, there is a better output.

Background radiation is originated from environmental radioactive sources cosmicandterrestrial.Materials distribution onsurface of the earth and height from sea level are not the same at various points.Absorbed dose caused by them were different at various points.In this research, Background radiation level inoutdoor different areas of Ilam province was measured and effective dose ratecaused by it was calculated.
RDS -110detector was used to measure background radiation. The metal base with a height of 1m was used for measuring at the same altitude and detector placed on the metal base. Outdoor backgroundradiationwas measured for seven points (The highest altitude, the lowest point North, South, East and West). Measured datawas entered to SPSS16 software for statistical operations. The mean equivalent dose rate andstandard deviation were calculated. By using the dosimetry calculations, the amount of annals effective dose rate in outdoor was calculated for different regions of Ilam province.
Findings: The mean equivalent dose rate caused by outdoor background radiation for different regions of Ilam province was obtained based on unit nSvh-1 include: Ilam 84 ± 10.67, Ivan 82 ± 10.71, Dehloran78 ± 12.61, Abdanan80 ± 11.21, Sirvan97 ± 15.50, Mehran 75 ± 10.31, Malekshahi88 ± 13.78, Dareshahr95 ± 14.15, Badreh85 ± 8.82 and Chardavol93 ± 13.20.The maximum outdoor equivalent dose rate was in Sirvan area with 97 ± 15.50nSvh-1 and minimum value in Mehran area with 75 ± 10.31nSvh-1. The average of outdoor annals equivalent dose rate in entire Ilam province 85.7± 7.5nSvh-1 in comparison average world 59nSvh-1 is more than 44%. Well as annual effective dose rate was 0.107±0.009nSvy -1.
Discussion & Ilam provincehasmore mean-annualequivalent dose rate and effective dose rate compared to global average annualequivalent dose rate and effective dose ratedue to mountainous and relatively high altitude from sea level.

Standards observation in imaging centers cause to patient dose reduction in patients and improving image quality. Identification standards and determine the gap own facilities with standard centers is a necessity for standardization. In this article, Standards level in imaging centers have been studied in Ilam province. Dose was measured in the controlled, monitored and uncontrolled region for each center. Czech list contains 210 items were prepared by using standard values in the world and Iran. Separately, Czech list were completed for each center. Level standard calculated at sections: building and construction, Preparation and usage of equipment, Protection of staff and patients, Patient rights and staff salaries for all hospitals and presented as percentage of standard. Level of patient information has been checked about radiation effects by using the questionnaire. Level of dose were standard in controlled monitored and uncontrolled region all of centers. Generally the level standards in Ilam imaging centers were obtained at sections: Building and construction 64.9 ℅, Preparation and usage of equipment 69.4℅, Protective staff and patients 80.03℅, Rights of patients 81.7℅ and staff rights almost 100%. Patient imaging centers were aware of effects of radiation on cell were 28%. In this study, the level of standard and distance to the full the level of standardization Were determined for all centers.The level of gap with completely standardization of imaging centers in the province is building and construction section35.1℅, preparing and application of equipment 30.6℅, Protection of staff and patients 19.97℅, Patient rights 18.3%. As well as patient imaging centers not informed about the effects of radiation on cells were 72%.

Identification and analysis of light elements using atomic layers due to low energy X ray is not a suitable method and They have weak energy and absorbed locally. Gamma rays have enough energy for detection. Nuclear techniques usually are used to identi-fy and analyze of light elements such as hydrogen، oxygen and etc that the major components of Tissues and drug. Nuclear methods have expensive equipment and high risk factor. Before using this equipment، the level of efficiency and all aspects of radiation protection issues measured by using computer codes such as MCNP. In this paper، a system designed can be used qualitative and quantitative analysis of tissues with in vivo and in vitro to investigate the changes of the elements percent، Observed dose rate of drug body tissue (spot check) and etc.

MCNP code has ability to transport and particle analysis a system was Designing for the analysis of light elements. The most important parameters were deter-mined and with ability of code to change the geometry of components determined an optimal point for each parameter. Effective Parameters in analysis Including material Component Sys-tem، Component dimensions and their shaped and located by writing several programs with MCNP code their parameters were studied and selected as the most suitable of them for sys-tem.

All parameters were evaluated in this study include: 1. With Research different ma-terial، beryllium oxide - Bismuth was chosen for collimator material. 2. change rate of flux with thickness of collimator was investigated، Result، no significant increase in the flux for 5cm thickness. 3. Flux rate was checked by changing Opening angle of collimator، It was found، collimator opening angle should be proportional to the radiation field. If collimator opening angle increase، Neutron scattering is increase and decrease opening angle flux rate will de-crease. 4. Output flux rate was check with changes collimator Length and found maximum point in 22cm collimator length. 5. Flux rate was checked by changing the distance of sample from source، It was found that would be better if their position nearest distance. 6. System dose calculations were performed It is quite standard. Discussion and

System designed According to the results of effective parameter of light elements analysis that all the optimized parameters and system works with using MCNP code simulation software. The system in Compared to other devices are used in light elements analysis such as reactors have smaller volume، higher utilization rate، less pollution and Lower cost. System is used for light element analysis in local and extensive tissues، monitoring of drugs in tissues and etc. Analysis results is given in (6) image.