نتایج جستجو برای: miniature neutron source

تعداد نتایج: 470706  

Journal: :iranian journal of radiation research 0
kakavand 1 department of physics, zanjan university, zanjan, iran ghafourian atomic energy organization of iran, tehran, iran haji-shafeieha 1 department of physics, zanjan university, zanjan, iran

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...

Ghafourian, Haji-Shafeieha, Kakavand,

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...

توکلی زانیانی, هاجر, نامی نظری, محمد, کلانتری, سید ظفرالله ,

One of the important neutron sources for Boron Neutron Capture Therapy (BNCT) is a nuclear reactor. It needs a high flux of epithermal neutrons. The optimum conditions of the neutron spectra for BNCT are provided by the International Atomic Energy Agency (IAEA). In this paper, Miniature Neutron Source Reactor (MNSR) as a neutron source for BNCT was investigated. For this purpose, we designed a ...

ژورنال: سنجش و ایمنی پرتو 2017

In this work investigated the determination of Selenium in wheat of Kashan's people's meal, via neutron activation analysis method (NNA) in “The Miniature Neutron Source Reactor” section. The γ transition produced in reaction of the neutron capture 77Se (n, γ) (T1/2= 17.4 s) was used to determine the concentration of Selenium, due to the rapid transfer of samples from th...

ژورنال: سنجش و ایمنی پرتو 2020

In this study, the neutron and gamma doses in the dry channel and in the internal irradiation site of the Miniature Neutron Source research reactor (MNSR) has been calculated and measured. The MNSR reactor is a light water reactor with a maximum power of 30 kW and equipped with various irradiation facilities, including five irradiated sites, five irradiation sites and a dry channel. The interna...

شامرادی‌فر, هادی, شهابی, ایرج, شیرانی, احمد,

In this work, the Isfahan Miniature Neutron Source Reactor (MNSR ) has been simulated using the MCNP code, and reactivity worth of flooding the inner irradiation sites of this reactor in an accident has been calculated. Also, by inserting polyethylene capsules containing water inside the inner irradiation sites, reactivity changes of this reactor in same such accident have been measured, the re...

صالحی, روح اله, طاهری, محمد, عبداله زاده, مسعود, قاسمی, عباس,

  Background : Performing successful BNCT experiments needs a suitable neutron source. Important factors of the neutron beam are flux and energy that are very important in the selection of neutron source. In most centers that use this method for treatment, reactor is a neutron source, which according to characteristics of the reactor appropriated neutrons are very high. High cost of constructin...

Journal: :iranian journal of radiation research 0
h. miri-hakimabad radiation detection and measurement laboratory, ferdowsi uinvesity of mashhad, mashhad, iran h. panjeh radiation detection and measurement laboratory, ferdowsi uinvesity of mashhad, mashhad, iran a. vejdani-noghreiyan radiation detection and measurement laboratory, ferdowsi uinvesity of mashhad, mashhad, iran

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 unwa...

Journal: :iranian journal of radiation research 0
jacob g. fantidis department of electrical engineering, eastern macedonia and thrace institute of technology, greece

background: monte carlo simulations play a vital role in the calculation of the necessary shielding both for neutrons and photons. advanced and simple shielding materials against neutron and gamma rays were compared by simulation using the mcnb4b monte carlo code. the simulations were carried out for the three common neutron sources, namely the 252cf, the 241am/be and the dd neutron generator w...

نمودار تعداد نتایج جستجو در هر سال

با کلیک روی نمودار نتایج را به سال انتشار فیلتر کنید