نتایج جستجو برای: iridium_192 monte carlo mcnp
تعداد نتایج: 72882 فیلتر نتایج به سال:
background: several landmine detection methods, based on nuclear techniques, have been suggested during the recent years. neutron energy moderation, neutron-induced gamma emission, neutron and gamma attenuation, and fast neutron backscattering are nuclear-based methods used for landmine detection. the aim of this study is to use backscattered neutron for landmine detection. materials and method...
In view of assessing natural radioactivity with on-site quantitative gamma spectrometry, efficiency calibration of NaI(Tl) detectors is investigated. A calibration based on Monte Carlo simulation of detector response is proposed, to render reliable quantitative analysis practicable in field campaigns. The method is developed with reference to contact geometry, in which measurements are taken pl...
Monte Carlo calculations and TLD measurements have been performed for the purpose of characterizing dosimetric properties of new commercially available brachytherapy sources. All sources tested consisted of a solid core, upon which a thin layer of 125I has been adsorbed, encased within a titanium housing. The PharmaSeed BT-125 source manufactured by Syncor is available in silver or palladium co...
Quantitative information on photon scattering around brachytherapy sources is needed to develop dose calculation formalisms capable of predicting dosimetric parameters with minimal empiricism. Photon absorption and scatter around brachytherapy sources can be characterized using the tissue attenuation factor, defined as the ratio of dose in water to water kerma in free space. In this study, the ...
The manganese bath method for measuring the neutron emission rate of radionuclide sources requires corrections to be made for emitted neutrons which are not captured by manganese nuclei. The Monte Carlo particle transport code MCNP has been used to calculate the fractions of neutrons that escape from the boundaries of the tank, that are captured by the steel cavity in which the source is housed...
AIM Exact knowledge of dosimetric parameters is an essential pre-requisite of an effective treatment in radiotherapy. In order to fulfill this consideration, different techniques have been used, one of which is Monte Carlo simulation. MATERIALS AND METHODS This study used the MCNP-4C to simulate electron beams from Neptun 10 PC medical linear accelerator. Output factors for 6, 8 and 10 MeV el...
در این پایان نامه با استفاده از کد محاسباتی mcnp (monte carlo n-particle)، ضرایب انباشت پرتودهی تابش های گاما (با در نظر گرفتن تمام برهم کنش های فوتون با ماده) در انرژی های 1 تا mev 100 برای چشمه ی نقطه ای همسانگرد در ضخامت های 1 تا mfp10 برای دو ماده آب و سرب محاسبه شده اند. نتایج به دست آمده در انرژی های پایین (تا mev15) با نتایج مراجع دیگر که در انرژی های پایین و شرایط مشابه ای ارائه شده اند...
Introduction: In recent decades, several Monte Carlo codes have been introduced for research and medical applications. These methods provide both accurate and detailed calculation of particle transport from linear accelerators. The main drawback of Monte Carlo techniques is the extremely long computing time that is required in order to obtain a dose distribution with good statistical accuracy. ...
background: two protocols of aapm tg-51 and iaea trs-398 were compared followed by a measurement and monte carlo simulation of beam quality correction factor, kq, aapm tg-51 and iaea trs-398 protocols were compared for the absorbed dose to water for dw, and kq parameters. materials and methods: dose measurements by either protocols were performed with cylindrical and plane parallel chambers for...
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