Results 61 to 70 of about 10,040 (154)
Journal of Applied Clinical Medical Physics, Volume 27, Issue 1, January 2026.Abstract Purpose This work presents the development and pilot implementation of a comprehensive remote (postal) dosimetry audit for Ir‐192 High Dose Rate interstitial brachytherapy, integrating independent experimental and computational dosimetry procedures into a unified workflow. Methods A compact, water‐equivalent phantom was designed to accommodate
Eleftherios P Pappas +8 more
wiley +1 more source
Medical Physics, Volume 53, Issue 1, January 2026.Abstract Background The Xoft electronic brachytherapy source is commonly used to treat superficial lesions and tumors located at shallow depths. However, uncertainties in material composition and geometry, mainly arising due to the manual assembly of the x‐ray tube components, contribute to inter‐source variability in the tube output spectrum.
Azin Esmaelbeigi +6 more
wiley +1 more source
Jurnal Fisika Flux, 2017 Criticality benchmark experiment at STACY critical facility is important for validation of computation technique and nuclear data library used in design of nuclear fuel cycle criticality safety.
Zuhair Zuhair +2 more
doaj +3 more sources
Geant4-related R&D for new particle transport methods
, 2009 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
Medical Physics, Volume 53, Issue 1, January 2026.Abstract Purpose To develop clinically relevant test cases for commissioning Model‐Based Dose Calculation Algorithms (MBDCAs) for 192Ir High Dose Rate (HDR) gynecologic brachytherapy following the workflow proposed by the TG‐186 report and the WGDCAB report 372.
Vasiliki Peppa +6 more
wiley +1 more source
BURNCAL: A Nuclear Reactor Burnup Code Using MCNP Tallies [PDF]
, 2002 BURNCAL is a Fortran computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in a nuclear reactor. The code uses output parameters generated by the Monte Carlo neutronics code MCNP to determine the isotopic inventory as a function of time and power density.
openaire +2 more sources
Re-engineering a nanodosimetry Monte Carlo code into Geant4: software design and first results
, 2009 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
Characterization of the light and flexible nonlead aprons as an alternative to Pb–PVC
Journal of Applied Clinical Medical Physics, Volume 26, Issue 12, December 2025.Abstract Background Radiation shielding is crucial for protecting healthcare professionals from scatter radiation during x‐ray procedures. Conventional lead aprons, although effective, are limited by their high weight, low flexibility, and potential toxicity.
Mansour Tayebi khorami, Zaker Salehi
wiley +1 more source
Monte Carlo with fuel burnup method for the ENHS benchmark calculations [PDF]
Nuclear Technology and Radiation Protection, 2003 Estimates of the uncertainties arising from approximations in the methods used in different nuclear data processing and neutron transport codes are usually obtained by inter-comparing calculations made using different code systems.
Milošević Miodrag 1 +2 more
doaj +1 more source
, 2018 Nanocomposites enable us to tune parameters that are crucial for use of such materials for neutron-optics applications such as diffraction gratings by careful choice of properties such as species (isotope) and concentration of contained nanoparticles ...
Blaickner, M. +12 more
core +4 more sources