Results 51 to 60 of about 2,139 (206)
Validation of Thermal Neutron Scattering Cross Sections for Heavy Water based on Molecular Dynamics Simulation [PDF]
EPJ Web of Conferences, 2019 Recently, the thermal scattering libraries of ENDF/B-VIII.0 and JEFF-3.3 for light and heavy water were released with a new water model (CAB model) proposed by Damian.
Hyun Haelee, Kim Do Heon, Lee Young-Ouk
doaj +1 more source
Simulations of a parallel plate Fission Chamber using the MCNPX simulation code
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2020 Abstract MCNPX in its latest version is able to simulate the transportation of Fission Fragments. It opens the door to Fission Chamber simulations. Such simulations are not straightforward and comparisons with experimental spectra often failed. A procedure is described in the present paper to perform such simulation and to process the result to ...
Mathieu, L., Aïche, M.
openaire +3 more sources
Gamma-Ray Attenuation Properties of Boron Carbide in Radiological Energy Range Using MCNPX Code
, 2021 The radiation attenuation parameters such as radiation mass attenuation coefficients (MAC), half value layer (HVL), mean free path (mfp) of boron carbide (B4C) have been calculated at radiological x-ray energies using MCNPX (version 2.6.0) general ...
Altunsoy, E. E. +4 more
core +1 more source
Design and Optimization of a Shield for Am-Be Source to Reduce Radiation Hazards Using MCNPX Code
International Journal of Environmental Health Engineering, 2022 Aim: Protection against nuclear radiation is one of the most important issues in nuclear technology and industries that use this technology. Among the types of radiation emitted from radioactive sources, neutron and gamma rays are among the most dangerous radiations due to lack of electrical charge and serious damage to living ...
Mohsen Nasri Nasrabadi +2 more
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MCNPX Model/Table Comparison [PDF]
, 2003 MCNPX is a Monte Carlo N-Particle radiation transport code extending the capabilities of MCNP4C. As with MCNP, MCNPX uses nuclear data tables to transport neutrons, photons, and electrons. Unlike MCNP, MCNPX also uses (1) nuclear data tables to transport
Hendricks, J S, Hendricks, J.S.
core +1 more source
Journal of Radiation Research and Applied Sciences, 2016 The application of Variance Reduction Techniques (VRT) in Monte Carlo (MC) codes brings significant improvement in efficiency and a significant profit in the time of simulation.
Maged Mohammed +4 more
doaj +1 more source
Radiation Shielding Features of Ordinary and High-Density Concretes Loaded With PbO Micro and Nanoparticles against High-Energy Photons [PDF]
Iranian Journal of Medical Physics, 2020 Introduction: The present study aimed to evaluate the impact of PbO nano and micro-sized fillers on ordinary and heavy concretes for different photon energies.
Khatibeh Verdipoor, Asghar Mesbahi
doaj +1 more source
Simulation of a beam rotation system for a spallation source
Physical Review Special Topics. Accelerators and Beams, 2015 With a nominal beam power of nearly 1 MW on target, the Swiss Spallation Neutron Source (SINQ), ranks among the world’s most powerful spallation neutron sources.
Tibor Reiss +4 more
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Meteoritics &Planetary Science, Volume 61, Issue 4, Page 565-579, April 2026.Abstract Surface processes on the asteroid Ryugu have been investigated using cosmic‐ray‐produced radionuclides, 10Be, 26Al, and 36Cl, and stable noble gases, on eight samples returned by the Hayabusa2 spacecraft. The 10Be and 26Al along with 21Ne measurements indicate that the two Chamber A samples A0105 collected during the first touchdown (TD) were ...
Kunihiko Nishiizumi +30 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.
core