Results 21 to 30 of about 15,370 (183)
X-ray and γ-ray Sensing from Aqueous-Based Lead Sulfide Telluride Nanocomposites. [PDF]
SmallPbSxTey nanoparticles integrate into flexible, size‐scalable aramid polymeric scaffolds, forming percolation paths capable of efficiently transporting the electrons and holes created by penetrating photonic interactions. The resulting nanosemiconductor‐nanofiber composite forms the basis for room‐temperature spectroscopic sensors of X‐rays and γ‐rays ...
Le VD +6 more
europepmc +2 more sources
Localization of nuclear materials in large concrete radioactive waste packages using photofission delayed gamma rays [PDF]
EPJ Web of Conferences, 2021 The characterization of radioactive waste packages is mandatory for their transport, interim storage and final disposal. In this framework, the Nuclear Measurement Laboratory of CEA DES IRESNE Institute, at Cadarache, France, uses a high-energy electron ...
Delarue Manon +10 more
doaj +1 more source
Elaborate SMART MCNP Modelling Using ANSYS and Its Applications
EPJ Web of Conferences, 2017 An MCNP 3-dimensional model can be widely used to evaluate various design parameters such as a core design or shielding design. Conventionally, a simplified 3-dimensional MCNP model is applied to calculate these parameters because of the cumbersomeness ...
Song Jaehoon +3 more
doaj +1 more source
Bremsstrahlung conversion efficiency and gamma - neutron generation from polypropylene, aluminum, iron, and lead bombarded by 10 MeV electrons [PDF]
Nuclear Technology and Radiation Protection, 2020 An electron beam from the UELR-10-15S2 accelerator (average energy of 9.92 ± 0.48 MeV) was applied to irradiate food and medical items at the Research and Development Center for Radiation Technology, Vietnam Atomic Energy Institute, Vietnam. The
Tuan Nguyen Anh, Tao Chau Van
doaj +1 more source
, 2009 The Reduced Enrichment Research and Test Reactor (RERTR) Program uses the REBUS-PC computer code to provide reactor physics and core design information such as neutron flux distributions in space, energy, and time, and to track isotopic changes in fuel and neutron absorbers with burnup.
Stevens, J. G. +1 more
openaire +2 more sources
MCNP: Multigroup/adjoint capabilities [PDF]
, 1994 This report discusses various aspects related to the use and validity of the general purpose Monte Carlo code MCNP for multigroup/adjoint calculations. The increased desire to perform comparisons between Monte Carlo and deterministic codes, along with the ever-present desire to increase the efficiency of large MCNP calculations has produced a greater ...
Wagner, J. C. +3 more
openaire +2 more sources
Analysis of DD, TT and DT Neutron Streaming Experiments with the ADVANTG Code [PDF]
EPJ Web of Conferences, 2020 The paper presents an analysis of DD, TT and DT neutron streaming benchmark experiments with the recently released hybrid transport code ADVANTG (AutomateD VAriaNce reducTion Generator).
Kos Bor +8 more
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
doaj +1 more source
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
Brazilian Journal of Radiation Sciences, 2021 MCNP is a code extensively used to simulate experiments involving transport of radiation using the Monte Carlo method. This code allows the study of different geometries, materials, and radiation types (e.g.
Caroline Mattos Barbosa +5 more
doaj +1 more source