نتایج جستجو برای: be neutron source

تعداد نتایج: 4518067  

ژورنال: سنجش و ایمنی پرتو 2020

Neutron Generators (NG) are used as a neutron source for different applications. During recent years, major efforts are underway to develop a high yield compact NG. In this way, radiation protection aspects need to be considered during the operation of these high yield NGs. In this paper the neutron effective dose of a NG operator has been calculated using MCNPX Monte Carlo code. The results sh...

Jamal Amiri

Introduction: The Monte Carlo simulation is used to enhance reliability in the experiments related to nuclear instruments. in addition, that is used to calculate the different components of the neutron and gamma ray fluxes in boron neutron capture therapy(BNCT) and neutron capture (NCT)applications. BNCT is one of the methods in radiotherapy, that is used the neutron beam for ki...

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

background: several landmine detection methods, based on nuclear techniques, have been suggested up to now. neutron-induced gamma emission, neutron and gamma attenuation, and fast neutron backscattering are the nuclear methods used for landmine detection. in this paper an optimized (safe and effective) moderating structure using an 241am-be neutron source for detecting landmines has been invest...

Introduction: Environmental and occupational human exposure from neutron source can lead to the serious biologic effects. The aim of this study is to evaluate the cancer incidence risk for various human organs at different neutron dose levels due to exposure from an Americium-241/Beryllium (Am-241/Be), a standard neutron source for calibration purposes. Material and Methods: We measured ambient...

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...

ژورنال: سنجش و ایمنی پرتو 2020

The inverse-square law is used to calculate the radiation flux at difference distances from the source. This law is applied for point source and point detector in vacuum. This research aims to study the point behavior of volumetric source and detector by undertaking required corrections on inverse-square law through the elimination of scattered neutrons contribution. The measurements have been ...

ژورنال: سنجش و ایمنی پرتو 2019

The 252Cf brachytherapy source is a spontaneous fission decay source, which is used as a neutron-emitting source. In addition to neutrons emitted from this source, gamma rays are also emitted with the average energy of 1 MeV. In this study, using the Monte Carlo N-Particle code (MCNPX), the absorbed dose rates of the neutrons, the primary gamma and the secondary gamma that generated by thermal ...

Alireza Sadremomtaz, Peyvand Taherparvar Sepideh Gholami

Introduction: In recent years, the use of neutrons has increased in various fields such as medicine and industry. One of the important applications of neutrons is in medical research. Neutrons have greater linear energy transfer than gamma rays and are considered more dangerous radiation. Hence, the detection and determination of neutron dose is a very important and vital issu...

D. Meena, H.S. Palsania, N. Chejara, N. Jakhar, P. Meena, S.K. Gupta,

Background: A 5 Ci 241Am-Be radio isotopic neutron source-based prompt gamma neutron activation analysis (PGNAA) setup was designed for estimation of minimum detectable concentration (MDC) of elements in aqueous solutions. Materials and Methods: Performance variables related to PGNAA setup (source to sample distance, sample to detector distance and volume of water) were optimized experimentally...

Journal: :journal of biomedical physics and engineering 0
m m firoozabadi university of birjand gh izadi vasafi k karimi-sh university of birjand m ghorbani

background: in neutron interaction with matter and reduction of neutron energy due to multiple scatterings to the thermal energy range, increasing the probability of thermal neutron capture by neutron captures makes dose enhancement in the tumors loaded with these materials.   objective: the purpose of this study is to evaluate dose distribution in the presence of  10 b ,  157 gd  and  33 s  ne...

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