نتایج جستجو برای: mcnp simulation code
تعداد نتایج: 704198 فیلتر نتایج به سال:
The csg2csg tool is a minimal dependency Python3 based program to facilitate the comparison of radiation transport Monte Carlo codes. can currently parse MCNP and OpenMC geometry descriptions, it subsequently export MCNP, FLUKA, PHITS, Serpent files. This translation achieved by reading input into class system objects corresponding surfaces, cells, materials so on. are then translated ‘generic’...
Introduction: The CT machine utilizes a bowtie filter to shape the X-ray beam and remove lower energy photons. Configuration of this bowtie filter is complex and its geometry is often not available in detail. It causes the CT dose index (CTDI) be with the different values in measurement versus Monte Carlo simulation studies and other analytical calculations. It is important esp...
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. ...
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...
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...
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 ...
In this paper, we show that a module implemented in the MCNP transport code to perform sensitivity analyses can be diverted topology optimizations of nuclear equipment. Component design with approach leads sophisticated solutions outperform their human-designed counterparts.
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...
Introduction: Development of a novel radiopharmaceutical needs assessment of its biological- distribution in animal models, most commonly mice prior to its common application. This study describes the biodistribution and absorbed dose prediction 131I-MIBG in human organs after injection in mice. Materials and Methods: In this research, 131I-MIBG radiopha...
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