Results 61 to 70 of about 6,588 (195)

The MCNPX Monte Carlo Radiation Transport Code

open access: yesAIP Conference Proceedings, 2007
MCNPX (Monte Carlo N‐Particle eXtended) is a general‐purpose Monte Carlo radiation transport code with three‐dimensional geometry and continuous‐energy transport of 34 particles and light ions. It contains flexible source and tally options, interactive graphics, and support for both sequential and multi‐processing computer platforms.
Laurie S. Waters   +7 more
openaire   +2 more sources

Responsive liquid metal materials towards unstructured environment

open access: yesResponsive Materials, Volume 4, Issue 1, February 2026.
Room‐temperature liquid metals integrate conductivity, deformability, and interfacial dynamics, enabling robust performance in unstructured environments. This review highlights key properties, requirements, and applications across in vivo, underwater, natural, space, and radiation settings, with advances in sensing, actuation, thermal regulation, and ...
Bo Yuan   +5 more
wiley   +1 more source

Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX

open access: yesAtom Indonesia, 2023
A novel simulation to calculate the neutronic parameters of the TRIGA 2000 reactor using plate-type fuel has been performed. The plate fuel used was produced by the Indonesian Nuclear Industry (PT INUKI) with U3Si2-Al material. Neutronic parameters based
A. Nuryana, R. S. N. Mahmudah, A. Khakim
doaj   +1 more source

Two-point theory for the differential self-interrogation Feynman-alpha method

open access: yes, 2012
A Feynman-alpha formula has been derived in a two region domain pertaining the stochastic differential self-interrogation (DDSI) method and the differential die-away method (DDAA). Monte Carlo simulations have been used to assess the applicability of the
C. Berglöf   +9 more
core   +1 more source

Monte Carlo Particle Lists: MCPL [PDF]

open access: yes, 2017
A binary format with lists of particle state information, for interchanging particles between various Monte Carlo simulation applications, is presented.
Cai, Xiao Xiao   +5 more
core   +2 more sources

Decommissioning Cost Estimate for the Ghana Research Reactor‐1 Facility Using the CERREX‐D2 Software

open access: yesScience and Technology of Nuclear Installations, Volume 2026, Issue 1, 2026.
The Ghana Research Reactor‐1 facility would certainly be decommissioned, either at the end of its life or by a decision to discontinue its operation. In planning for GHARR‐1’s eventual decommissioning, estimating the overall decommissioning cost is a major activity that needs to be undertaken to support budgeting and decision‐making for the project. To
Emmanuel K. Boafo   +4 more
wiley   +1 more source

Medidas experimentais e simulação MCNPX para avaliar coeficiente de atenuação linear e mássico de catalisador ativado utilizado no processo de FCC.

open access: yesBrazilian Journal of Radiation Sciences, 2020
O Craqueamento Catalítico Fluido (FCC) é um processo usado na indústria petroquímica para converter algumas frações de petróleo que são mais pesadas em frações mais leves, como gasolina e GLP, por exemplo.
Victor Hugo Farias Ferreira da Silva   +7 more
doaj   +1 more source

Calculation of NaI(Tl) detector efficiency using 226Ra, 232Th, and 40K radioisotopes: Three-phase Monte Carlo simulation study

open access: yesOpen Chemistry, 2022
Thallium-activated sodium iodide (NaI(Tl)) detectors can be used in gamma cameras, environmental radiation assessments, including radiation emission levels from nuclear reactors, and radiation analysis equipment.
Tekin Huseyin Ozan   +5 more
doaj   +1 more source

Study of CdTe detector response functions using different MCNPX computational modeling detailing

open access: yesBrazilian Journal of Radiation Sciences
The spectra measured with cadmium telluride (CdTe) detectors show high spectral distortions that must be corrected by applying a mathematical algorithm along with the detector's response functions.
A. M. Antunes   +5 more
doaj   +1 more source

Determination of Neutron Flux in Brain Cancer Boron Neutron Capture Therapy Using Monte Carlo Simulation

open access: yesPhysics Communication, 2022
Boron Neutron Capture Therapy (BNCT) is a relatively safer technology for killing cancer cells, one of which is the Glioblastoma multiforme. One of the main components of the BNCT equipment is the collimator which functions as an exit point for ...
Fajar Arianto   +3 more
doaj   +1 more source

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