Results 41 to 50 of about 15,503 (186)
COMPARISON OF WASTE DUE TO IRRADIATED STEELS IN THE ESFR AND DEMO [PDF]
EPJ Web of Conferences, 2021 For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design.
Reid Jack +4 more
doaj +1 more source
Brazilian Journal of Radiation Sciences, 2021 Aqueous Homogeneous Reactors (AHRs) or simply solution reactors present nowadays a promising alternative to produce medical isotopes, especially 99Mo. The AHR medical production concept has been proposed to produce medical isotopes directly in the fuel ...
Daniel Milian Pérez +5 more
doaj +1 more source
Reducing the radioactive doses of liquid samples taken from reprocessing plant vessels by volume reduction [PDF]
, 2007 A
Buyst, Jimmy +2 more
core +2 more sources
Introducing an Optimized Computing Method to Improve Parallel-Hole Collimators’ Response in Nuclear Medicine [PDF]
مجله علوم و فنون هستهای, 2019 Performance of parallel-hole collimators may be evaluated by determining their response to a point radioactive source which for instance, the amount of collimator resolution is calculated by measuring the full width at half maximum (FWHM) of point spread
V Moslemi, M Ashoor
doaj +1 more source
Comparison between GEANT4 and MCNP for well logging applications [PDF]
EPJ Web of Conferences, 2023 MCNP and GEANT4 are two reference Monte Carlo nuclear simulators, MCNP being the standard in the Oil & Gas nuclear logging industry. While performing a simulation benchmark of these two software for the purpose of “Cased Hole” wellbore evaluation ...
Varignier Geoffrey +8 more
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Neutron spectrometer for fast nuclear reactors [PDF]
, 2015 In this paper we describe the development and first tests of a neutron spectrometer designed for high flux environments, such as the ones found in fast nuclear reactors.
Angelone, M. +10 more
core +2 more sources
MCNP: Neutron benchmark problems [PDF]
, 1991 The recent widespread and increased use of radiation transport codes has produced greater user and institutional demand for assurances that such codes give correct results. Responding to these requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on criticality, pulsed sphere, and shielding neutron ...
Whalen, D. J. +3 more
openaire +2 more sources
The Failure of Monte Carlo Radiative Transfer at Medium to High Optical Depths [PDF]
, 2018 Computer simulations of photon transport through an absorbing and/or scattering medium form an important research tool in astrophysics. Nearly all software codes performing such simulations for three-dimensional geometries employ the Monte Carlo ...
Baes, Maarten, Camps, Peter
core +2 more sources
, 1997 The Monte Carlo code MCNP-DSP was developed from the Los Alamos MCNP4a code to calculate the time and frequency response statistics obtained from subcritical measurements. The code can be used to simulate a variety of subcritical measurements including source-driven noise analysis, Rossi-{alpha}, pulsed source, passive frequency analysis, multiplicity,
openaire +3 more sources
Evaluation of mass attenuation coefficient of concrete sample for different traits
Brazilian Journal of Radiation Sciences, 2022 Concrete is widely used in the world and is the main material for civil construction. Due to its properties, it has different uses such as structural, filling and shielding. The aim of this work is to compare experimental and theoretical mass attenuation
Luan Ferreira Bastos +7 more
doaj +1 more source