Results 1 to 10 of about 2,318 (135)

Generation of 3D reference dosimetric datasets towards adoption of model-based dose calculations for permanent implant prostate brachytherapy. [PDF]

open access: yesMed Phys
Abstract Purpose This work aims to create and validate a comprehensive set of test cases and 3D reference dosimetric datasets for model‐based dose calculation algorithms (MBDCAs) in permanent implant prostate brachytherapy. These test cases address the limits of the standard TG‐43 formalism towards improving dose evaluations in prostate cancer ...
Akbari F   +8 more
europepmc   +2 more sources

Correlation of size specific dose estimates with organ dose in abdominal spectral computed tomography [PDF]

open access: yesJ Appl Clin Med Phys
Abstract Background In abdominal spectral Computed Tomography (CT), organ dose assessment is important for radiation safety but remains challenging due to the complexity of Monte Carlo (MC) simulations. Purpose This study aimed to compare the correlations of three size‐specific dose estimate (SSDE) metrics (including the central slice SSDEcenter, the ...
Qin T   +6 more
europepmc   +2 more sources

<i>Vitess 3.8</i>: a modernized framework for Monte Carlo neutron tracing simulations. [PDF]

open access: yesJ Appl Crystallogr
VITESS 3.8 introduces modernized neutron‐source modeling with new artificial‐intelligence‐based and KDSource modules, plus expanded component support including a prism module and NCrystal‐integrated sample module. It also delivers major upgrades to existing modules and multiple new features, advancing the simulation framework.VITESS is a modular Monte ...
Robledo JI   +5 more
europepmc   +2 more sources

SCIENTIFIC WORKFLOWS FOR MCNP6 AND PROTEUS WITHIN THE NEAMS WORKBENCH [PDF]

open access: yesEPJ Web of Conferences, 2021
In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling and Simulation (NEAMS)Workbench.
Dominesey Kurt A.   +3 more
doaj   +1 more source

BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS [PDF]

open access: yesEPJ Web of Conferences, 2021
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, including, shielding, material lifetime and remote maintenance ...
Valentine A.   +3 more
doaj   +1 more source

Analysis of the Signal over Noise Ratio of the hodoscope determined by Monte Carlo calculation [PDF]

open access: yesEPJ Web of Conferences, 2021
The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA) for the purpose of the CABRI International Program (CIP), managed by IRSN in the ...
Di Salvo J., Mirotta S., Chevalier V.
doaj   +1 more source

Assessment of the gamma and neutron dose field around the closed-water activation loop at the JSI TRIGA reactor [PDF]

open access: yesEPJ Web of Conferences, 2023
A closed-water activation loop is being built at the Jožef Stefan Institute TRIGA reactor in Slovenia to serve as a well-defined and stable source of high-energy gamma rays and neutrons.
Kotnik Domen, Snoj Luka, Lengar Igor
doaj   +1 more source

Elimination of Aflatoxins from Two Selected Nigerian Vegetable Oils using Magnetic Chitosan Nanoparticles

open access: yesIndustria: Jurnal Teknologi dan Manajemen Agroindustri, 2021
Activated charcoal and imarsil (local adsorbent) had shown significant Aflatoxin (AF) decontamination potentials in vegetable oil at a low AF contamination level of ≤ 9 ng/L.
Oluyinka Eunice Aringbangba   +4 more
doaj   +1 more source

Determination of steel and lead bi-laminated shielding for military vehicles

open access: yesBrazilian Journal of Radiation Sciences, 2023
In the present work, the transmission factors of γ-rays are determined in bi-layered shields composed of lead and steel, through a methodology composed of three distinct parts.
Ary Machado de Azevedo   +4 more
doaj   +1 more source

Determination of backscattered neutrons/gammas from open beam port of a research reactor [PDF]

open access: yesEPJ Web of Conferences, 2020
Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor.
Jazbec Anže   +4 more
doaj   +1 more source

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