Results 81 to 90 of about 4,292 (208)
The MCNPX Monte Carlo Radiation Transport Code
AIP Conference Proceedings, 2007 MCNPX (Monte Carlo N‐Particle eXtended) is a general‐purpose Monte Carlo radiation transport code with three‐dimensional geometry and continuous‐energy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multi‐processing computer platforms.
Laurie S. Waters +7 more
openaire +2 more sources
Medical Physics, Volume 51, Issue 8, Page 5604-5617, August 2024.Abstract Background With recent interest in patient‐specific dosimetry for radiopharmaceutical therapy (RPT) and selective internal radiation therapy (SIRT), an increasing number of voxel‐based algorithms are being evaluated. Monte Carlo (MC) radiation transport, generally considered to be the most accurate among different methods for voxel‐level ...
Gunjan Kayal +7 more
wiley +1 more source
Implementation of the CEM-Code into the MCNPX-Code [PDF]
, 1998 In the development stage of improving the physics abilities of MCNPX, the CEM code has been implemented into MCNPX as the nuclear reaction model for nuclei and pion induced reactions up to 5 GeV of kinetic energy.
Gallmeier, F.X.
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Characterizing the voxel‐based approaches in radioembolization dosimetry with reDoseMC
Medical Physics, Volume 51, Issue 6, Page 4007-4027, June 2024.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
Modelling radiation transport in voxel geometries with the Monte Carlo code MCNPX
, 2004 The paper summarizes the research activities at ENEA Bologna to develop a voxel option within the Monte Carlo code MCNPX. An integrated methodology (MCNPX-VOXEL) has been presented that solves the radiation transport problem in voxel geometries and is ...
G. Gualdrini +4 more
core +1 more source
Journal of Astronomy and Space SciencesThe 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
Application of the MCNPX-McStas interface for shielding calculations and guide design at ESS
, 2014 Recently, an interface between the Monte Carlo code MCNPX and the neutron ray-tracing code MCNPX was developed [1, 2]. Based on the expected neutronic performance and guide geometries relevant for the ESS, the combined MCNPX-McStas code is used to ...
Nonbøl, E. (author) +6 more
core +1 more source
MCNPX-PoliMi Variance Reduction Techniques for Simulating Neutron Scintillation Detector Response. [PDF]
, 2012 Scintillation detectors have emerged as a viable He–3 replacement technology in the field of nuclear nonproliferation and safeguards. MCNPX–PoliMi is a Monte Carlo Code that has been used for simulating detailed scintillation physics; however, until now,
Prasad, Shikha
core +3 more sources
International Journal of Energy Research, Volume 2024, Issue 1, 2024.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
, 2022 Boron Neutron Capture Theraphy (BNCT) salah satu metode radioterapi yang memanfaatkan interaksi boron-10 dan neutron termal yang menghasilkan partikel lithium beserta partikel alfa.
Imam sapi’i, 4211415022
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