In this paper, we show that concentrations of manufactured carbon-based nanoparticles (MCNPs) in aquatic sediments will be negligible compared to levels of black carbon nanoparticles (BCNPs). This is concluded from model calculations accounting for MCNP sedimentation fluxes, removal rates due to aggregation or degradation, and MCNP burial in deeper sediment layers. The resultant steady state MC...

introduction: in this paper, by complete definition of human eye containing the various parts and their materials, the difference between this model and a homogeneous water phantom are compared for two ophthalmic plaques using 125i and 103pd. material and methods: the simulation of the two phantoms were performed in the mcnp-4c code and by using the geometry of a three-dimensional eye, differen...

BACKGROUND Obtaining high quality images in Single Photon Emission Tomography (SPECT) device  is the most important goal in nuclear medicine. Because if image quality is low, the possibility of making a mistake in diagnosing and treating the patient will rise. Studying effective factors in spatial resolution of imaging systems is thus deemed to be vital. One of the most important factors in SPE...

A non destructive technique based on gamma spectrometry and application of the Monte Carlo method for detector efficiency calibration, was used to assay radioactive content waste drums. Exploranium GR-130 miniSPEC portable gamma ray spectrometer was used to externally monitor radioactive waste drums containing ion exchange resin waste from the water demineralization system of GRR-1 open pool-ty...

Underwater vehicle is designed to ensure the security of country sea boundary, providing harsh requirements for its power system design. Conventional power sources, such as battery and Stirling engine, are featured with low power and short lifetime. Micronuclear reactor power source featured with higher power density and longer lifetime would strongly meet the demands of unmanned underwater veh...

Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is critical input to the design and validation many aspects reactor design, including, shielding, material lifetime remote maintenance requirements/scheduling. Neutronics studies, which perform in-depth analysis are typically performed using transport codes such as MCNP, TRIPOLI, Serpent, FLUKA OpenMC....

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...