نتایج جستجو برای: be neutron source

تعداد نتایج: 4518067  

Journal: :iranian journal of radiation research 0
m.r. deevband department of biophysics, tarbiat modares university, tehran, iran p. abdolmaleki department of biophysics, tarbiat modares university, tehran, iran m.r. kardan nuclear sciences research school, radiation applications research school, tehran, iran h.r. khosravi nuclear sciences research school, nuclear sciences and technology research institute, tehran, iran m. taheri national radiation protection department, iranian nuclear regulatory authority, tehran, iran f. nazeri national radiation protection department, iranian nuclear regulatory authority, tehran, iran

background: the poly-allyl diglycol carbonate (padc) detector is of particular interest for development of a fast neutron dosimeter. fast neutrons interact with the constituents of the cr-39 detector and produce h, c and o recoils, as well as (n, α) reaction. these neutron- induced charged particles contribute towards the response of cr-39 detectors. material and methods: electrochemical etchin...

ژورنال: سنجش و ایمنی پرتو 2019

Neutron radiography is an unique, advanced and useful non-destructive test method in various industries and researches. Nuclear reactors are powerful and stable neutron sources for the neutron radiography system. In this research, the MNSR research reactor has been used as a neutron source for a neutron radiography system, and its neutron beam parameters have been evaluated. Also, using the dir...

ژورنال: سنجش و ایمنی پرتو 2014

In order to simulate neutron shields, MCNP5 calculation code was used and three types of homogeneous and separated shield multilayer arrangement, irradiated with 241Am-Be neutron sources were investigated. In these shields, the polyethylene (C2H4) and polystyrene (C8H8) were used as moderator material, and the boron carbide (B4C), as a thermal neutron absorber material and stainless steel as a ...

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Neutron dose-equivalent buildup factors were calculated for point isotropic neutron sources irradiating infinite slablike shields of lead, iron and water using the MCNP code. The factors are presented for some source neutron energies in the range from 0.025 eV to 14 MeV, and for shield thicknesses from 0.5 to 10 mfp. Since the MCNP code considers all kinds of neutron interactions with matter, a...

Alireza Sadremomtaz, Peyvand Taherparvar Sepideh Gholami

Introduction: Neutrons have many applications in various fields, such as medicine. The important application of neutron in medical science is in Boron Neutron Capture Therapy (BNCT). Because of this, determination of neutron dose and flux is critical for the health maintaining of workers and patients exposed to this beam. The neutron radioisotope sources produce gamma rays in ...

Background: The amount of average dose enhancement in tumor loaded with 10B may vary due to various factors in boron neutron capture therapy.Objective: This study aims to evaluate dose enhancement in tumor loaded with 10B under influence of various factors and investigate the dependence of this dose enhancement on neutron spectra changes.Material and Methods: In this simulation stud...

Journal: :journal of biomedical physics and engineering 0
m t bahreyni toossi medical physics department, faculty of medicine, mashhad university of medical sciences, mashhad, iran b khajetash medical physics department, faculty of medicine, mashhad university of medical sciences, mashhad, iran m ghorbani medical physics department, faculty of medicine, mashhad university of medical sciences, mashhad, iran

background: one of the main causes of induction of secondary cancer in radiation therapy is neutron contamination received by patients during treatment. objective: in the present study the impact of wedge and block on neutron contamination production is investigated. the evaluations are conducted for a 15 mv siemens primus linear accelerator.  methods: simulations were performed using mcnpx mon...

Journal: :iranian journal of science and technology (sciences) 2009
m. haji-shafeieha

beryllium chemical combination has a considerable effect on the design and fabrication of the241am9be neutron source. in this investigation the beryllium combinations were studied as a generator ofneutrons with various mass percentage, and the neutron yields were also calculated using the results of thealice and srim codes calculations per unit incident charge. the neutron yields of beryllium ...

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