In the current paper, a novel technique is represented to control liquid petrochemical and petroleum products passing through transmitting pipe. A simulation setup, including an X-ray tube, detector, pipe, was conducted by Monte Carlo N Particle-X version (MCNPX) code examine two-by-two mixture of four diverse (ethylene glycol, crude oil, gasoline, gasoil) in various volumetric ratios. As featu...

Abstract Introduction: The present study aimed to investigate the radiation protection properties of silicon-based composites doped with nano-sized Bi 2 O 3 , PbO, Sm Gd WO 3, and IrO particles. Radiation shielding nanoparticles were investigated for first time in current study. Material methods: MCNPX (2.7.0) Monte Carlo code was utilized calculate linear attenuation coefficients single multi-...

i131 is a famous radio-iodine isotope in use for diagnosis and treatment of hyper functioning and cancerous thyroid gland. it is a nuclear reactor product; however nuclear reactor may be unavailable in some areas. replacement by i-124 may be possible, another iodine isotope producible by cyclotron; a system more available than reactor. here absorbed fraction of gamma and beta rays of i-124 thro...

Abstract To enhance the production of medium-heavy, neutron-rich nuclei, and to facilitate measurements independent yields neutron-induced fission, a proton-to-neutron converter dedicated ion guide for fission have been developed IGISOL facility at University Jyväskylä. The holds fissionable targets, products emerging from targets are collected in helium gas transported downstream experimental ...

A novel free release measurement facility (FRMF) was developed within the joint research project "Metrology for Radioactive Waste Management" of the European Metrology Research Programme. Before and during FRMF design and construction, Monte Carlo calculations with MCNPX and PENELOPE codes were used to optimize the thickness of the shielding, the dimensions of the container, and the shape of de...

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...