Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor
Somaye
Bagheri
Ph.D. Student, School of Mechanical Engineering, Shiraz University, Shiraz, Iran
author
Hosein
Khalafi
Professor, Nuclear Science and Technology Research Institute, AEOI, Tehran, Tehran, Iran
author
Seyed Mohammad
Mir Vakili
Assistant Professor, Nuclear Science and Technology Research Institute, AEOI, Tehran, Tehran, Iran
author
text
article
2014
per
The purpose of this research is feasibility study of irradiating the rod type control fuel element consists of UO2 fuel rods with 3-5% enrichment in Tehran research reactor with respect to neutronic criteria. Rod type control fuel assembly has 12 fuel rods with 1.36 cm outer diameter arranged in a 3 by 4 lattice with 1.633cm pitch. In order to perform reactivity worth analysis, loading of the rod type fuel with 3-5% of enrichment in TRR reference core have been studied and possibility of loading rod type fuel assembly in TRR core is investigated from the neutronic viewpoint. Then for safety analysis and evaluation of the under moderated conditions, calculation of optimum pitch and radius of rod fuels with 3-5% enrichment have been performed and finally rod type control fuel assembly with 3.34% enrichment have been chosen as fuel, . Loading this fuel in three arrangement of TRR core has been studied from the neutronic viewpoint. Results show that by loading the rod type control fuel assembly in the TRR core, all operating conditions from the neutronic viewpoint are satisfied and irradiation test will not induce any reduction of the reactor safety.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
1
15
https://jrnt.guilan.ac.ir/article_1964_6cd121cc9668baef850cf942d2049383.pdf
Assessment of image quality in myocardial SPECT with increased number of projections: A Monte Carlo simulation study
Maryam
Rezaei
M.Sc. Student, Tarbiat Modares University, Tehran, Iran
author
Hosein
Rajabi
Associated Professor, Tarbiat Modares University, Tehran, Iran
author
Mohammad ali
Asgari
Ph.D. Student, Tarbiat Modares University, Tehran, Iran
author
text
article
2014
per
In this paper, we studied the effect of increasing number of projections in Myocardial SPECT from 32 to 64 while maintaining imaging time, on the final parameters of image quality using MonteCarlo simulation. Simulations performed by SimSET Monte Calro code on NCAT humanoid digital torso phantom. Three groups of images were simulated. First group with 32 projections and average 100k counts per view. The second group was simulated with 64 projections and average 50k counts per view for maintaining simulation time constant, and third group simulated with 64 projections but average 600k counts per view as reference. FBP method was use for reconstruction. Resolution, contrast and SNR parameters were calculated in each group and compared to each other. Increasing number of projections while reducing average counts per view, resulted to improvement of wall to cavity and wall to background contrasts. Reducing average counts per view caused a reduction in SNR value. In resolution comparison using FWHM, improvement was observed. According to FBP mathematical theory and effect of number of projections in reconstructed image, contrast enhancement was expectable. In nuclear medicine imaging, SNR would decrease by reducing the number of photons due to the statistical nature of radioactive decay. This reduction can cause some blurring in the reconstructed images that would be suppressed by increased number of projections. These phenomena leaded to resolution enhancement. It can be concluded that increasing in number of projection while decreasing number of photons could results enhancement in contrast and resolution.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
17
26
https://jrnt.guilan.ac.ir/article_1965_08d7bc28bd5a07c8561a5bbd0c534ff4.pdf
Numerical Modeling of VVER-1000 Coolant Channels in Transient Core Inlet Flowrate Condition
ghonche
baghban
دانشجوی دکتری، سازمان انرژی اتمی، تهران، ایران
author
Mohsen
Shaieste
دانشیار، دانشگاه امام حسین (ع)، تهران، ایران
author
Majid
Bahonar
استادیار، دانشگاه آزاد اسلامی واحد علوم و تحقیقات تهران، تهران، ایران
author
text
article
2014
per
Due to importance of nuclear reactors safety, numerical modeling of VVER-1000 coolant channels in transient core inlet flowrate is discussed. To do this, core of the Bushehr VVER-1000 reactor is divided into four channels. Then, termohydraulic parameters of each channel including coolant and fuel temperature distributions and pressure drop of channels is calculated. For these calculations, a program is developed by Fortran90 programming language. The obtained results from both program and RELAP5 code are compared. Good consistency of compared results verified the developed program.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
27
37
https://jrnt.guilan.ac.ir/article_1245_61bd01db2da9210b37f8586fbd48359c.pdf
The Design of a BNCT Treatment Room with a 20MeV Electron Accelerator
Masomeh
Soleimaninia
M.Sc., Application of Radiation Research, Nuclear Science & Technology Research Institute, Atomic Energy Organization of Iran.
author
Faeze
Rahmani
Assistant Professor, Physics Department, K.N. Toosi University of Technology, Tehran, Iran.
author
text
article
2014
per
In this paper, the BNCT treatment room has been proposed. Assumed neutron source was based on the photoneutron generated from 20MeV Linac. It was assumed that the designed treatment room with inner area equal to 7×9 m2 has been made of ordinary concrete. To reduce sum of photon and neutron dose rate less than 1µSv/hr behind the wall, the thickness of primary and secondary walls was calculated 180 cm and 150 cm, respectively. The window which is considered to monitor the patient situation from outside the room was consisted of 40 cm mineral oil, 70 cm lead glass and 40 cm plain glass. As the entrance of the room, two-bend maze with equivalent length of 13 m has been designed. Thickness of 26 cm ordinary concrete with thin layers of lead on their both sides has also been considered for the door at the entrance of the maze.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
39
52
https://jrnt.guilan.ac.ir/article_1966_d7b018363e7e67366325cee92009191a.pdf
Mammographic Image Enhancement Using Wavelet Transform
fatemeh
majidi
دانشگاه آزاد اسلامی واحد علوم و تحقیقات یزد
author
ALIMOHAMMAD
LATIF
عضوهییٔت علمی دانشگاه یزد
author
JAMILEH
MALAKOUTI
عضو هییٔت علمی دانشگاه علوم پزشکی تبریز
author
HAMED
KASAYI
کارشناس پژوهشکده مواد پژوهشگاه علوم و فنون هسته ای
author
text
article
2014
per
Mammography is the most effective method for the early diagnosis and treatment of breast cancer diseases. Mammographic images contain low signal to noise ratio and low contrast, hence it becomes too difficult for radiologists to analyze mammogram. To deal with above stated problems, it’s very important to enhance the mammographic images using image processing methods.More recently multiscale techniques have sparked the interest of the researchers for contrast enhancement of the images, especially wavelet transform This paper introduces a new image enhancement approach for mammographic images, which uses low pass filter, modified mathematical morphology, wavelet transform and homomorphic filter to suppress the noise of images. For performance evaluation of the proposed algorithm, contrast improvement index (CII) and edge preservation index (EPI) are adopted. Experimental results on mammographic images from databases show that the proposed algorithm improved contrast improvement index and edge preservation index so we can reach to the goal of enhancing mammographic images using wavelet transform.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
53
60
https://jrnt.guilan.ac.ir/article_1246_be5a0fc740de70a37d0fe8ddc9d2f48f.pdf
Designing graphical user interface and filter for PF simulation
Mohsen
Mohebi Nejad
M.Sc. Student, School of Modern Technology, University of Esfahan, Isfahan, Iran
author
Babak
Shirani
Assistant Professor, School of Modern Technology, University of Esfahan, Isfahan, Iran
author
Hosein
Pirjamadi
M.Sc. Student, School of Modern Technology, University of Esfahan, Isfahan, Iran
author
text
article
2014
per
Plasma Focus (or as a short PF) is a neutron generator. This device produce focused plasma, and have neutron and electron flux when it contained deuterium and tritium gases. Plasma focus device works on 5 phases. In this paper, different phases are simulated by Lee's code. This code is available as an excel file named "RADPF" and Charts output of this code are optimized data for plasma focus device. Due to its low graphical setting, ambiguity of the user interface and impossibility of experimental data receiving, the code performance is low. In order to make user-friendly to get the data of oscilloscope signals, we added the graphical interface and signal filtering to it.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
1
v.
2
no.
2014
61
67
https://jrnt.guilan.ac.ir/article_1967_36b1248dc5c2db3e3c9cd67f72cd433b.pdf