Results 81 to 90 of about 5,690 (213)
Optimizing the shielding properties of strength-enhanced concrete containing marble
The purpose of this study is to develop a low cost, locally produced concrete mixture with optimum marble content. The resulting mixture would have enhanced strength properties compared to the non-marble reference concrete, and improved radiation ...
A. Abdel-Latif M. +3 more
doaj +1 more source
Characterizing the voxel‐based approaches in radioembolization dosimetry with reDoseMC
Abstract Background Yttrium‐90 (90Y$^{90}{\rm {Y}}$) represents the primary radioisotope used in radioembolization procedures, while holmium‐166 (166Ho$^{166}{\rm {Ho}}$) is hypothesized to serve as a viable substitute for 90Y$^{90}{\rm {Y}}$ due to its comparable therapeutic potential and improved quantitative imaging.
Taehyung Peter Kim, Shirin A. Enger
wiley +1 more source
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri +4 more
wiley +1 more source
The safety of electronic components used in aerospace systems against cosmic rays is one of the most important requirements in their design and construction (especially satellites).
Ali Alizadeh, Gohar Rastegarzadeh
doaj +1 more source
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
Radiation damage assessment of the sixth SINQ target irradiation program based on MCNPX simulation
The 6th SINQ Target Irradiation Program (STIP VI) was conducted in SINQ Target 9 during 2011 and 2012. A radiation damage assessment based on a simulation using the MCNPX code was performed to obtain the irradiation parameters of displacement damage ...
D. Aulet +3 more
semanticscholar +1 more source
Performance Evaluation of Car Cargo Scanner Systems for Determining Linear Attenuation Coefficients of Aluminum Metal Sheets: Modeling [PDF]
This study has investigated the performance of the car scanner cargo system in determining the linear attenuation coefficient of aluminum metal from the images obtained from a modeled car scanner imaging system.
Amir Mohammad Beigzadeh, Mojtaba Askari
doaj +1 more source
Calculation of Detection Efficiency for the Gamma Detector using MCNPX
Radiation detection has been a main interest for researchers as all kind of produced particles in atomic and subatomic physics based on the measurement systems so-called detector. Detection efficiency is one of the main parameter in detection system besides many other different parameters of the detector.
Mesbahi, A. +2 more
openaire +4 more sources
MCNP/MCNPX model of the annular core research reactor. [PDF]
Many experimenters at the Annular Core Research Reactor (ACRR) have a need to predict the neutron/gamma environment prior to testing. In some cases, the neutron/gamma environment is needed to understand the test results after the completion of an experiment.
DePriest, Kendall Russell +2 more
openaire +2 more sources

