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Characterization of a new shielding rubber for use in neutron–gamma mixed fields
element, calculations with MCNPX 2.6 code confirmed that the incorporation of 5 weight percentage (wt%) of boron carbide exhibited the best performance as a thermal neutron absorber. A series of both experimental and simulation results are provided...
Calculation of the Dose of Samarium-153-Ethylene Diamine Tetramethylene Phosphonate (153Sm-EDTMP) as a Radiopharmaceutical for Pain Relief of bone Metastasis
distribution of 153Sm-EDTMP in bone and other tissues, using MCNPX Monte Carlo code in the particle transport model.
Materials and Methods
Dose delivery to the bone was simulated by seeking radiopharmaceuticals on the bone surface. The phantom...
Comparison of light transport-incorporated MCNPX and FLUKA codes in generating organic scintillators responses to neutrons and gamma rays
The NE102 plastic scintillator response to 137Cs gamma rays and NE213 liquid scintillator response to both mono-energetic and 241Am–Be neutrons have been modeled using FLUKA׳s EVENTBIN and MCNPX׳s PTRAC cards. The comparison made in different energy...
A quantitative PGNAA study for use in aqueous solution measurements using Am-Be neutron source and BGO scintillation detector
A prompt gamma neutron activation analysis (PGNAA) system including an Am–Be neutron source and BGO scintillation detector are used for quantitative analysis of bulk samples. Both Monte Carlo-simulated and experimental ...
Longitudinal response uniformity of a rectangular-shaped plastic scintillator when exposed to mono-energetic gamma-rays
capture therapy (BNCT). The MCNPX-PHOTRACK hybrid code has been used to model the response of rectangular plastic scintillator of partially painted surface in order to reduce as much as possible the longitudinal non-uniformity which usually exist in large...
effects of respiratory motion to dosimetry body organs with radiation external photon
. The heart, liver, lung, stomach, spleen are selected becuse they were rigidly translated with the motion of the diaphragm during breathing. The percent of dose variations into geometries AP and PA and 0.08 MeV energy were obtained by MCNPX as following: lung...
The Effects of Breasts Shielding on Dose Reduction in CT Examinations
were calculated for UF revised ORNL family of six anthropomorphic phantoms using MCNPX. Siemens DRH was simulated and the Monte Carlo model included parameters that specify its source geometry and x-ray energy spectrum.
Considering the fact...
دوزجذبی بتا و گامای یُد131 در تیروئید کروی و استوانه ای با استفاده از کد ّFLUKA و مقایسه آن با نتایج کد MCNPX
ید 131 به طور گسترده در درمان پرکاری و سرطان تیروئید به کار می رود که شاید موفقترین نوع درمان در مقایسه با سایر داروها باشد. هدف اصلی در درمان با پرتو این است که تومور حداکثر دوز کشنده را به صورت یکنواخت، و بافتهای سالمِ ...
استفاده از ید125برای براکی تراپی تومورهای مغزی
In this paper used 125I as radioactive source for brachytherapy of brain tumor, to do this used the simulation code MCNPX and put the tumor in 12 regions of the brain from 0.5 to 2.5 cm for the radius of the tumor. The results were compared...
Which factors affect on Estimation of absorbed dose and effective dose
an uncertainty less than 0.5%. MCNPX code and ORNL modified adult phantom are applied for the dose assessment in the energy range 10-9 - 20 MeV, under AP, PA, RLAT, LLAT, ROT and ISo irradiation conditions. The results are then normalized to the unit of neutron...