Results 41 to 50 of about 10,040 (154)

Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

open access: yesNuclear Engineering and Technology, 2017
To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cores were selected and used for a benchmark test of the important parameter keff.
Kabach Ouadie   +4 more
doaj   +1 more source

New antineutrino energy spectra predictions from the summation of beta decay branches of the fission products [PDF]

open access: yes, 2012
In this paper, we study the impact of the inclusion of the recently measured beta decay properties of the $^{102;104;105;106;107}$Tc, $^{105}$Mo, and $^{101}$Nb nuclei in an updated calculation of the antineutrino energy spectra of the four fissible ...
Algora, A.   +16 more
core   +5 more sources

New para‐hydrogen cold neutron source at the Budapest Research Reactor: Monte Carlo simulations

open access: yesJournal of Applied Crystallography, Volume 59, Issue 2, Page 392-403, April 2026.
This paper explores the options for upgrading the cold neutron source at the Budapest Research Reactor.The planned upgrade of the neutron guide system at the Budapest Research Reactor (BRR) provides an opportunity to enhance the performance of its cold neutron source.
Dmitrii Shapiro   +3 more
wiley   +1 more source

Recent Developments in the MCNP-POLIMI Postprocessing Code [PDF]

open access: yes, 2004
The design and analysis of measurements performed with organic scintillators rely on the use of Monte Carlo codes to simulate the interaction of neutrons and photons, originating from fission and other reactions, with the materials present in the system and the radiation detectors.
openaire   +2 more sources

Measurements of ultracold neutron upscattering and absorption in polyethylene and vanadium

open access: yes, 2013
The study of neutron cross sections for elements used as efficient ``absorbers'' of ultracold neutrons (UCN) is crucial for many precision experiments in nuclear and particle physics, cosmology and gravity.
Adamek, Evan R.   +29 more
core   +1 more source

Underwater detection of dangerous substances: status the SABAT project [PDF]

open access: yes, 2017
The Neutron Activation Analysis (NAA) plays an exceptional role in the modern nuclear engineering, especially in detection of hazardous substances. However, in the aquatic environment, there are still many problems to be solved for effective usage of ...
Moskal, P.   +5 more
core   +2 more sources

Initial study of regolith exposure ages and burial conditions on Ryugu: Cosmogenic nuclides score in two touchdowns

open access: yesMeteoritics &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

TRIPOLI-4® calculations of neutron multiplicity counting rates of 3He array detectors and verification tests of an automatic MCNP-to-TRIPOLI conversion tool for recent ICSBEP subcritical experiments [PDF]

open access: yesEPJ Web of Conferences
TRIPOLI-4® is a general-purpose Monte Carlo radiation transport code developed at CEA Paris-Saclay center. It uses continuousenergy nuclear data to simulate neutron transport for diverse nuclear engineering fields.
Lee Yi-Kang
doaj   +1 more source

USE OF MONTE CARLO SIMULATIONS FOR OPTIMAL GEOMETRY STUDY IN CALCULATION OF ATTENUATION COEFFICIENT FOR ELEMENT, COMPOUND AND MIXTURE

open access: yesBrazilian 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

Monte Carlo modelling of pixel clusters in Timepix detectors using the MCNP code

open access: yesPhysica Medica, 2022
The track structure of the signal measured by the semiconductor pixel detector Timepix3 was modelled in the Monte Carlo MCNP® code. A detailed model at the pixel-level (256 × 256 pixels, 55 × 55 µm2 pixel size) was developed and used to generate and store clusters of adjacent hit pixels observed in the measured data because of particle energy ...
Jaroslav Šolc   +7 more
openaire   +2 more sources

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