نتایج جستجو برای: mcnp x

تعداد نتایج: 623959  

سلیمانیان, ویشتاسب, قاسمی, حسن, مختاری, علی, پیامی, فریدون,

In this paper in order to achieve a suitable spectrometer for nuclear radiation detection at room temperature, effect of adding the element Hg to binary compound semiconductor ZnTe was studied completely. Electronic structure and transport properties of ternary compound semiconductor ZnxHg(1-x)Te (ZHT) simulated using ABINIT as a computational code based on density functional theory. According ...

2011
D. Krstic D. Nikezic

Series of mathematical phantoms of human body, given by Oak Ridge National Laboratory (ORNL), was programmed as input files for MCNP-4B code. Detailed check of geometry of these phantoms performed by MCNP-4B, discovered some minor errors, that resulted in overlapping of some organs. Three types of errors were found and described here: (a) colon overlaps with pelvis bone; (b) facial skeleton pen...

2009
M. E. Sawan B. Kiedrowski B. Smith A. Ibrahim R. Slaybaugh E. P. Marriott

An innovative computational tool (DAG-MCNP) has been developed for efficient and accurate 3-D nuclear analysis of geometrically complex fusion systems. Direct coupling with CAD models allows preserving the geometrical details, eliminating possible human error, and faster design iterations. DAG-MCNP has been applied to perform 3-D nuclear analysis for several fusion designs and demonstrated the ...

Journal: :Boletin De La Sociedad Espanola De Ceramica Y Vidrio 2022

The effect of substitution Pb2O3 by CuO content was studied for 75% Li2B4O7 + (25 − x)Pb2O3 xCuO glass system where x = 0, 5, 10, 15, 20, and 25 wt%. mechanical radiation shielding properties were evaluated the investigated samples. included Young's, shear, bulk, longitudinal, Poisson ratio, micro-hardness computed theoretically based on packing factor (Vi) dissociation energy (Gi) metal oxides...

Journal: :Indonesian Journal of Physics and Nuclear Applications 2016

Journal: :IOP conference series 2022

Abstract Monte Carlo N-Particle (MCNP) is a widely-used code in nuclear engineering, but it needs high computation times due to the tracking of every single particle and interaction event. This causes shielding optimization using trial-and-error take long complete. It can be solved by multiprocessing, this requires MCNP source which difficult obtain. Therefore, paper aims suggest solution on ho...

Journal: :Radiation Oncology (London, England) 2006
Carlos Esquivel Clifton D Fuller Robert G Waggener Adrian Wong Martin Meltz Melissa Blough Tony Y Eng Charles R Thomas

BACKGROUND Treatment of choroidal melanoma with radiation often involves placement of customized brachytherapy eye-plaques. However, the dosimetric properties inherent in source-based radiotherapy preclude facile dose optimization to critical ocular structures. Consequently, we have constructed a novel system for utilizing small beam low-energy radiation delivery, the Beamlet Low-kVp X-ray, or ...

پایان نامه :وزارت علوم، تحقیقات و فناوری - دانشگاه اراک - دانشکده علوم پایه 1390

نوترون تراپی با بور یا bnct یک روش موثر در درمان انواع تومورها به خصوص تومورهای مغزی است. اساس این روش بمباران ناحیه تومور نشاندار شده با بور-10 توسط نوترون های با شدت و انرژی مناسب است. ذرات ناشی از واکنش جذب نوترون در هسته های بور، انرژی خود را در ناحیه ای قابل مقایسه با ابعاد سلولی تخلیه کرده و باعث نابودی آن می شوند. در این رساله طیف انرژی نوترون راکتور مینیاتوری اصفهان mnsr برای bnct بهین...

Journal: :Medical physics 2005
C Avila J Lopez J C Sanabria G Baldazzi D Bollini M Gombia A E Cabal C Ceballos A Diaz Garcia M Gambaccini A Taibi A Sarnelli A Tuffanelli P Giubellino A Marzari-Chiesa F Prino E Tomassi P Grybos M Idzik K Swientek P Wiacek L M Montaño L Ramello M Sitta

Dual-energy mammographic imaging experimental tests have been performed using a compact dichromatic imaging system based on a conventional x-ray tube, a mosaic crystal, and a 384-strip silicon detector equipped with full-custom electronics with single photon counting capability. For simulating mammal tissue, a three-component phantom, made of Plexiglass, polyethylene, and water, has been used. ...

2015
Zeyun Wu Robert E. Williams

In reactor calculations, a detailed 3-D power density distribution is required for core optimization studies and safety analyses. The general Monte Carlo based neutral particle transport tool, MCNP [1], has the capability to obtain detailed power density distribution in a reactor through its criticality calculation mode (KCODE mode). However, there is no standard tally type in MCNP that is able...

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