Calculation of kinetic parameters Tehran Research Reactor using MCNPX code and compare the results with perturbation method and reference
Hamidreza
khaleghi
ندارم
author
text
article
2016
per
In this stady, (1 / v Poisoning Method) or perturbation method to calculate the kinetic parameters Tehran Research Reactor as Effective multiplication factor (Keff), effective delayed neutrons fraction (βeff) and prompt life time (ℓ) is used. . The purpose of this study is that there are errors in the values of these parameters especially neutron lifetime (ℓ) which is calculated first by MCNPX Code, shall be reduced and a more reasonable number To be earned. By working in this way is, the first, kinetic parameters of Tehran Reactor with enriched to 20% that Tehran Reactor now works with this Enriched ,calculated and Effective multiplication factor (Keff), effective delayed neutrons fraction(βeff), and the prompt lifetime (ℓ) is obtained. then some of poison that is boron is injected into the reactor and again this parameter is calculated. And finally, the values of these kinetic parameters calculated in both cases before and after the toxin injection, in particular, neutron lifetime (ℓ) with the reference value in the Tehran reactor (FSAR) were compared. Compare data show that the value of error, these parameters In particular neutron lifetime (ℓ) in the state after toxin injection is reduced and value of this parameters to the amount of those in Tehran reactor reference has been closer.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
1
7
http://jrnt.guilan.ac.ir/article_1973_24ffbbd1526fcadceb98e46e5317ea0c.pdf
Study of the fission dynamics of the excited nuclei synthesized in the reaction 18O+192Os in the framework of the Langevin equations
Hadi
Eslamizadeh
عضو هیات علمی دانشگاه
author
Frozan
Bagheri
M.Sc. student
author
fatemeh
Arefzadeh
دانشجوی کارشناسی ارشد
author
text
article
2016
per
In the framework of dynamical model and considering Langevin equations have been studied the evolution of the excited nuclei produced in fusion reaction 18O+192Os. The average multiplicity of pre-scission neutrons and fission probability have been calculated for the nuclei produced in the reaction 18O+192Os with considering viscosity of the nuclear matter as a free parameter. According to reproduction of experimental data on the pre-scission neutron multiplicity and fission probability has been extracted information about the magnitude of viscosity during transition to the saddle point and scission point. It was shown that for reproducing of the experimental data on the pre-scission neutron multiplicity and fission probability, it is necessary the magnitude of viscosity of nuclear matter increases with increasing excitation energy of the compound nuclei. Furthermore, the variation of viscosity as a function of excitation energy was determined for the nuclei produced in the reaction 18O+192Os during transition to the saddle point and scission point.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
8
14
http://jrnt.guilan.ac.ir/article_1974_bc37704903fa6e4741f52256cbd44f8f.pdf
Review of the mechanisms of ionizing radiation effect on removal of organic, mineral and microbial pollutants from effluent in combination with different chemicals and photocatalysts
حمایت
عسگری لجایر
گروه علوم و مهندسی خاک، دانشکده کشاورزی دانشگاه تبریز
author
نصرتاله
نجفی
گروه علوم و مهندسی خاک، دانشکده کشاورزی دانشگاه تبریز
author
ابراهیم
مقیسه
پژوهشکده کشاورزی هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران
author
text
article
2016
per
Concentration of population and industries in different parts has produced the large volume of wastewater, so that the lack of adequate treatment plants and no attention to proper treatment and pollutants removal techniques has created many environmental problems. The use of ionizing radiation alone to remove pollutants from wastewater needs high absorbed doses and may not be economical on an industrial scale. The application of photocatalytic and chemicals additives to induce oxidizing or reducing species depending on the type of pollutants have suggested for reducing the ionizing radiation dose to remove organic, inorganic and microbial contaminants. There was no study about combination of ionizing radiation with chemicals additives and photocatalysts in Iran, so that the introduction of these technologies and their impact mechanisms is required. According to application of sewage and wastewater mainly in the crops cultivation in Iran and entering of organic and inorganic contaminants to food chain by consumption of these plants, using of modern methods in removing contaminants from wastewater including combination techniques of ionizing radiation and compliance of added effluent with relevant standards is necessary. The present study investigates the mechanisms of integration of ionizing radiation such as gamma and electron beam with photocatalytic and chemicals additives such as methanol, tert-butanol, thiourea, hydrogen peroxide, ozone, pH, various gases, titanium dioxide and etc. to remove of organic, inorganic and biological contaminants and factors affects these mechanisms.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
15
29
http://jrnt.guilan.ac.ir/article_1975_9c6fc5864d118114f23a794f23857e0d.pdf
Determination the Strength of a 241Am-Be Neutron Source
akbar
abdi saray
دانشجوی سال آخر دکتری
author
محمد حسین
استکی
دانشیار دانشگاه اصفهان
author
جمشید
خورسندی
دانشیار سازمان انرژی اتمی
author
text
article
2016
per
Neutrons are used for medical, shielding and material research. The neutron has a greater linear energy transfer, and is considered a perilous radiation in comparison with gamma-rays. In recent years the use of (α, n) neutron sources are increased because of their high neutron yield. 241Am-Be is one of them that is widely used in many research centers and universities as a calibration source of neutron radiation. To calculate dose rates of Gamma and neutron from 241Am-Be source, measure its intensity, is one of the essential and important tasks. Strength of a 241Am-Be Neutron Source determined by the BF3 detector with the spatial integration method and error of the experiment, with applied corrections by Dysprosium and Gold foils has been reduced to less than 10.30%. Also, the 241Am-Be neutron source, BF3 detector and water tank were simulated with a Monte Carlo method and there is a good agreement between simulation and experimental results.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
30
42
http://jrnt.guilan.ac.ir/article_1976_67d47df4741d26130ffe8dad23bee00d.pdf
The interaction of a high-intensity laser pulse with plasma in a laser fusion in the presence of an obliquely external magnetic field
mojan
mobaraki
دانشگاه گیلان
author
ساعد
جعفری
عضو هیات علمی دانشگاه گیلان
author
text
article
2016
per
In recent years, the interaction of ultrashort laser pulses with solid target for applications in inertialconfinement fusion project has been regarded. In order to ignite a target fuel capsule in an inertialconfinement fusion by laser, the central region as called hot spot must be heated as much possible tomaximize the initial self-heating effect. In this article, to achieve the fusion of hydrogen-boron fuel isused the model block acceleration of plasma by laser-plasma interaction. By considering Maxwell's andhydrodynamic equations, it can be observed that with the increase of obliquely external magnetic field ,the pulse is focused and the dielectric permittivity of the plasma increases. It is obtained that withincreasing the Ѳ -angle, the angle between B0 and x-axis, the oscillations of the electron densitydistribution and the dielectric permittivity of the plasma are increased. So, in these conditions withoutthe use of a powerful laser pulses and just by changing the angle, the threshold energy in hot spotdecreases. Besides, the thermal conductivity of electrons reduced, it can be said that the thresholdenergy decreases and this represents an improvement of conditions for fusion.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
43
52
http://jrnt.guilan.ac.ir/article_1977_46f0e75c31751695b39388282c7a8b13.pdf
Cancer Risk Estimating for Various Organs Du to Accidentally Released Radionuclides from Bushehr Nuclear Power Plant Based on BEIR VII Model
mir rashid
hosseini aghdam
calibration labrator-Atomic energy organazation of iran
author
نعیم الدین متاج
کجوری
سازمان انرژی اتمی. پژوهشگاه علوم و فنون هسته ای
author
سید محمود رضا
آقامیری
دانشگاه شهید بهشتی. گروه مهندسی پرتوپزشکی. دانشکده ی هسته ای
author
رحمان
قراری
سازمان انرژی اتمی. پژوهشگاه علوم و فنون هسته ای
author
حمیدرضا
همتی
دانشگاه شهید بهشتی. گروه مهندسی پرتوپزشکی
author
text
article
2016
per
Abstract As we know the nuclear reactors in normal operating conditions, always allowable amount of radioactive materials release into environment according to the Thus, nuclear reactors protections have particular important from the health physics aspect. The main objective of this study is to assess the cancer risk using BIER VII models for various organs due to accidentally released radioactive material from Bushehr nuclear power plant stack and within various distances around of reactor. At first, it is assumed due to the ventilation system of reactor stack perturbation, human error or any other factors removal of radioactive materials will be exceeded. For this purpose, Hotspot2.7 software has been used. Then in the various classes’ atmosphere conditions for the wind average speeds of 2 and 14 m/s and various radii, amount of the total effective dose is calculated. Then, using the BIER VII equations, cancer risk is evaluated for various organs in the various male and female ages. TED has been obtained for different distances and average wind speeds 2 and 14 m/s at the steady state atmospheric condition, the cancer risk for ages upper 5 year is evaluated for the maximum distribution dose around the Bushehr Nuclear Power Plant. According to the obtained results, there is an inverse relation between distributed dose and wind speed. Therefore, amount of the absorbed dose rate by the reactor staff and crowd of the reactor around in the low wind speed is more. Also, cancer risk for ages under 10 year special female is more.
Journal of Radiation and Nuclear Technology
University of Guilan
2423-6616
3
v.
1
no.
2016
53
64
http://jrnt.guilan.ac.ir/article_2050_cc0b5245bbe88eea15d96af20d8dcb3b.pdf