Results 101 to 110 of about 25,046 (241)
This presentation shares exercises that utilize the NJOY input deck in 235 U material calculations.
openaire +2 more sources
A comparative study of clinically used fast Monte Carlo dose engines for proton therapy
Abstract Background Several fast Monte Carlo (MC) codes have been implemented and used to simulate proton transport and calculate patient doses in proton therapy. The resulting dose is typically compared to full MC codes, rather than other fast MC codes.
Sherif M. Gadoue, Narayan Sahoo
wiley +1 more source
To facilitate the timely execution of System Threat Reviews (STRs) for DNDO, and also to develop a methodology for performing STRs, LANL performed comparisons of several radiation transport codes (MCNP, GADRAS, and Gamma-Designer) that have been previously utilized to compute radiation signatures.
Marc Klasky +3 more
openaire +2 more sources
Research Progress on Radiation Volt‐Effect Isotope Cells
This review systematically summarizes the latest advances in radiation voltaic nuclear batteries based on perovskite materials as well as conventional semiconductors such as silicon, gallium arsenide, silicon carbide, gallium nitride, titanium dioxide, zinc oxide, diamond, and gallium oxide, highlighting the unique potential of perovskites for high ...
Qiannan Zhao +16 more
wiley +1 more source
Geant4-related R&D for new particle transport methods
A R&D project has been launched in 2009 to address fundamental methods in radiation transport simulation and revisit Geant4 kernel design to cope with new experimental requirements.
Augelli, M. +13 more
core +1 more source
Despite extensive efforts in studying radioactive aerosols, including the transmission of radionuclides in different chemical matrices throughout the body, the internal organ-specific radiation dose due to inhaled radioactive aerosols has largely relied ...
Khaled Talaat +3 more
semanticscholar +1 more source
ANALYSIS OF FAST NEUTRON TRANSPORT IN CHLORIDE SALTS USING MONTE CARLO METHOD
The aim of this paper is to present results of fast neutron behavior analysis within the chloride salts environment using simulations based on Monte Carlo method (MCNP 6.2).
Ondřej Šťastný +4 more
doaj +1 more source
Operation of a 1-Liter-Volume Gaseous Argon Scintillation Counter
We have built a gas-phase argon ionization detector to measure small nuclear recoil energies (< 10 keVee). In this paper, we describe the detector response to X-ray and gamma calibration sources, including analysis of pulse shapes, software triggers ...
A. Bernstein +23 more
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Non‐compliant neutron dose associated with an internal lead slab in a radiotherapy treatment vault
Abstract Background In high energy radiotherapy treatment vaults, photoneutrons can be produced by direct photon interactions with barrier materials and have a mean energy of approximately 20% of the nominal photon energy. Excess photoneutrons outside a treatment vault are always a concern due to their significant radiobiological efficacy, or Q value ...
Eduardo Galiano +2 more
wiley +1 more source
Re-engineering a nanodosimetry Monte Carlo code into Geant4: software design and first results
A set of physics models for nanodosimetry simulation is being re-engineered for use in Geant4-based simulations. This extension of Geant4 capabilities is part of a larger scale R&D project for multi-scale simulation involving adaptable, co-working ...
Gargioni, E., Grichine, V., Pia, M. G.
core +1 more source

