نتایج جستجو برای: mcnp code

تعداد نتایج: 168334  

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. ...

Journal: :Radiation research 2017
David Welch Leah Turner Michael Speiser Gerhard Randers-Pehrson David J Brenner

Anatomically accurate phantoms are useful tools for radiation dosimetry studies. In this work, we demonstrate the construction of a new generation of life-like mouse phantoms in which the methods have been generalized to be applicable to the fabrication of any small animal. The mouse phantoms, with built-in density inhomogeneity, exhibit different scattering behavior dependent on where the radi...

1996
M. A. Lone

Total neutron yield, integrated over the neutron energy and emission angle, is calculated for spaJlation reactions in lead at proton energies between 0.4 and 2 GeV. The computations were made with the LAHET/MCNP code package using the intranuclem-cascade-evaporation m o d e l o f B e r t i n i . T h e dependence of the integrat neutron yield on the target dimensions is investigated and the cont...

2011
Tran Van Hung

The neutron temperature is a characteristic parameter in irradiation channels of reactor. For nuclides which have resonances in the thermal neutron energy range, their Westcott g-factors are different from unity. The values of g-factors and cross-sections of (n, γ) reaction of these nuclides are temperature dependence. The standard energy for tabulation of thermal neutron cross-section (σ0) is ...

2015
Yue Guan Shifei Shen Hong Huang

A great number of radioactive cesium were released into sea water after Fukushima Accident. We modified the Regional Oceanic Modelling System (ROMS) to reproduce the dispersion process of the cesium in oceans. The simulated water concentration was in good agreement with observation. In order to explore the nuclear impact of these contaminant in ocean, we established a food web model to calculat...

Journal: :Journal of environmental radioactivity 2016
Giorgia Cinelli Laura Tositti Domiziano Mostacci Jonathan Baré

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...

2003
Jan Kyncl

The contribution deals with numerical solution to the problem of criticality for neutron transport equation using the source iteration method. Especially question of convergence of iterations is examined. It is inferred that a slow convergence can be expected if optical thickness of the space region considered is large. For such a case it is next shown that the results may strongly be affected ...

2007
Jouni Uusi–Simola Sami Heikkinen Petri Kotiluoto Tom Serén Tiina Seppälä Iiro Auterinen Sauli Savolainen

Radiation sensitive polymer gels are among the most promising three-dimensional dose verification tools developed to date. Polymer gel dosimeter known by the acronym MAGIC has been tested for evaluation of its use in boron neutron capture (BNCT) dosimetry. We irradiated a large (diameter 10 cm, length 20 cm) cylindrical gel phantom in the epithermal neutron beam of the Finnish BNCT facility at ...

2003
R. M. Keyser

The use of germanium detectors for the identification and quantification of radionuclides in unknown and non-standard counting geometries has increased in the recent past with the need to clean up and verify sites used for radionuclide processing, smuggling detection and other purposes. The calculation of the amount of radionuclide present requires a knowledge of the efficiency of the detector ...

2013
Y. C. Hsu R. J. Sheu

This study intends to predict the scope of neutron production and induced radioactivity for two therapy accelerators in Taiwan: 235 MeV proton and 400 MeV/A carbon ion accelerators. For radiation safety concern, much effort has been put into associated benchmark calculations to ensure the quality of predictions. Two Monte Carlo codes FLUKA and MCNPX were applied to calculate the neutron yield f...

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