Results 81 to 90 of about 8,745 (215)
Introducing a Method to Derive a Multiple Virtual Point Source Model of Linac for Photon Beam Dose Calculation Using Monte Carlo Method [PDF]
In this study a new simple but a very effective method is introduced for the beam modeling of the invariant part of a medical linear accelerator. In this method, instead of segmentation of scoring plane and analysis of phase space file, the mirror image ...
I Jabbari +3 more
doaj
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
MCNP output data analysis with ROOT (MODAR)
MCNP Output Data Analysis with ROOT (MODAR) is a tool based on CERN's ROOT software. MODAR has been designed to handle time-energy data issued by MCNP simulations of neutron inspection devices using the associated particle technique.
C. Carasco (8093471)
core +2 more sources
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
The Monte Carlo transport workhorse, MCNP, is undergoing a massive renovation at Los Alamos National Laboratory (LANL) in support of the Eolus Project of the Advanced Simulation and Computing (ASCI) Program.
Mosteller, R. D. (Russell D.) +13 more
core
Recent MCNP developments [PDF]
MCNP is a widely used and actively developed Monte Carlo radiation transport code. Many important features have recently been added and more are under development.
Briesmeister, J.F., Hendricks, J.S.
core
The MCNP code development program is a relatively large and rapidly changing project in the small and highly-specialized field of radiation transport, specifically radiation protection and shielding.
Hendricks, J. S.
core
Automatic Conversion of MCNP Geometries to TRIPOLI-4®
International audienceThe manual conversion of geometrical models for Monte Carlo particle-transport codes is a long and difficult task, especially for complex models of large facilities.
Mancusi, Davide
core +1 more source
Optimization of Neutron Detection Module based on Li-Glass scintillator and an array of SIPMs [PDF]
Wengrowicz Udi +8 more
doaj +1 more source
MCNP{trademark} Monte Carlo: A precis of MCNP
MCNP{trademark} is a general purpose three-dimensional time-dependent neutron, photon, and electron transport code. It is highly portable and user-oriented, and backed by stringent software quality assurance practices and extensive experimental ...
Adams, K.J.
core

