نتایج جستجو برای: mcnp simulation code

تعداد نتایج: 704198  

Journal: :iranian journal of radiology 0
lida gholamkar department of medical radiation engineering, science and research branch, islamic azad university, tehran, iran ali asghar mowlavi physics department, hakim sabzevari university, sabzevar, iran; international center for theoretical physics (ictp), associate federation scheme, medical physics field, trieste, italy; physics department, hakim sabzevari university, sabzevar, iran. tel: +98-5144012521 mahdi sadeghi radiation application research school, nuclear science and technology research institute, tehran, iran mitra athari department of medical radiation engineering, science and research branch, islamic azad university, tehran, iran

conclusion by comparing the results, we saw that w/rh anode/filter combination is the best choice in breast mammography imaging because of the lowest delivered dose in comparison with w/ag and rh/al. moreover, breast thickness and g value have significant effects on mgd. objectives the aim of this study was to determine the average absorbed dose of x-ray radiation in the glandular tissue of the...

2012
Fatemeh Sadat Rasouli Seyed Farhad Masoudi

Introduction BNCT is an effective method to destroy brain tumoral cells while sparing the healthy tissues. The recommended flux for epithermal neutrons is 10 n/cms, which has the most effectiveness on deep-seated tumors. In this paper, it is indicated that using D-T neutron source and optimizing of Beam Shaping Assembly (BSA) leads to treating brain tumors in a reasonable time where all IAEA re...

As the input of MCNP code (Monte Carlo N - Particle code system), a monoenergetic and isotropic point source with the energy rangeg from 0.3 to 10 MeV was placed at the center of a spherical material surrounded by another one. The first shielding material was water and the second one was lead. The total thickness of the shield varied between 2 to 10 mfp. Then, using the output of MCNCP, exposur...

2012
Matthew R. Halstead Sangjin Lee James Petrosky Abigail Bickley Paul Sokol

The energy spectrum of the Neutron Radiation Effects Program (NREP) beam line, Target-ModeratorReflector-1 (TMR-1), at Indiana University has not been previously characterized. The facility has a unique proton source with variable pulse length (15-600 s) and energy (13 MeV). Thus, it can produce a unique and tailored neutron beam when incident on a beryllium target. Through a combination of MCN...

2007
Shaun Clarke Thomas Downar Sara Pozzi Marek Flaska John Mihalczo Enrico Padovani Alan Hunt

This work illustrates a methodology based on photon interrogation and coincidence counting for determining the characteristics of fissile material. The feasibility of the proposed methods was demonstrated using the Monte Carlo-based MCNPX/MCNPPoliMi code system capable of simulating the full statistics of the neutron and photon field generated by the photon interrogation of fissile and non-fiss...

ژورنال: سنجش و ایمنی پرتو 2020

Developing well logging methods will increase the applications of logs related to all the other geology sciences. Well logging curves introduce the essential information to evaluate reservoir characterizations, rock type and also formation fluid properties quantitatively. One of the most important parts of drilling and completion operations which affect making decision about the future planes i...

2010
A. Mehranian M. R. Ay H. Zaidi

We introduce a fast and well-structured package for constructing voxel-based computational phantoms as MCNP(X) input file based on CT DICOM images. Our program which has been implemented under a graphic user inter-face provides several basic image processing tools for manipulating images. The MCNP materials are interpreted from the CT numbers of DICOM images. Two modes of phantom creation have ...

Journal: :Arab Journal of Nuclear Sciences and Applications 2018

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: :iranian journal of radiation research 0
t.p. faez physical oceanography department, azad university, tehran, iran s. sarkar department of medical physics, tehran university of medical sciences, tehran, iran

abstract

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