Results 21 to 30 of about 1,181 (179)
An MCNPX accelerator beam source
Progress in Nuclear Energy, 2009 Abstract We have developed a new source feature for MCNPX that enables the transport of particles in a field-free drift region for a beam produced by an accelerator. The beam representation is based on the formulation used in the TRANSPORT charged-particle-beam code.
Joe Durkee +4 more
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Journal of Medical Physics, 2021 Purpose: The aim of this research was to calculate the fluence, dose equivalent (DE), and kerma of thermal, epithermal and fast photoneutrons separately, within ICRU soft-tissue-equivalent phantom in the radiotherapy treatment room, using MCNPX Monte ...
Mojtaba Cheraghian +3 more
doaj +1 more source
Low-energy neutron propagation in MCNPX and GEANT4 [PDF]
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 2006 Simulations of neutron background from rock for underground experiments are presented. Neutron propagation through two types of rock, lead and hydrocarbon material is discussed. The results show a reasonably good agreement between GEANT4, MCNPX and GEANT3 in transporting low-energy neutrons.
Lemrania, R. +5 more
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Status of the MCNPX Transport Code [PDF]
, 2001 The Monte Carlo particle transport code MCNPX and its associated data have been the focus of a major development effort at Los Alamos for several years. The system has reached a mature state, and has become a significant tool for many intermediate and high-energy particle transport applications.
H. G. Hughes +14 more
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Open Chemistry, 2022 We present the findings of an extensive examination on newly designed CdO-rich and transparent glass shields for nuclear medicine facilities in lieu of traditional and unfavorable materials, such as lead and concrete.
Erdemir Rabiye Uslu +7 more
doaj +1 more source
Americium-beryllium shield container optimization with new high alloyed stainless steel and composite material using MCNPX code [PDF]
Nuclear Technology and Radiation Protection, 2023 In this paper the goal is to optimize a shield for the americium-beryllium radioactive source, which generates a mixed neutron and gamma-ray radiation field, using two different materials designed with simultaneous moderation and absorption of ...
Hooshmand Fini Ali +2 more
doaj +1 more source
Validation of MCNPX-PoliMi fission models [PDF]
2012 IEEE Nuclear Science Symposium and Medical Imaging Conference Record (NSS/MIC), 2012 We present new results on the measurement of correlated, outgoing neutrons from spontaneous fission events in a Cf-252 source. 16 EJ-309 liquid scintillation detectors are used to measure neutron-neutron correlations for various detector angles. Anisotropy in neutron emission is observed.
Sara A. Pozzi +12 more
openaire +1 more source
Brazilian Journal of Radiation Sciences, 2020 O Instituto Nacional do Câncer José Alencar Gomes da Silva - INCA adota como protocolo padrão no tratamento de câncer de próstata, na técnica de Radioterapia Tridimensional Conformada (3D-CRT), o uso da incidência do feixe em 4 angulos, 0°, 90º , 180º e ...
Eduardo Fonseca +5 more
doaj +1 more source
Evaluation of fast fission factor in a typical pool type research reactor [PDF]
Journal of Nuclear Research and Applications, 2022 One of the important factors of a nuclear reactor core is the fast fission factor. This paper calculates this parameter based on space and energy-dependent method using the PTRAC card of MCNPX code. Tehran research reactor (TRR) is taken as a case study,
M. Arkani, S. Khakshournia
doaj +1 more source
Brazilian Journal of Radiation Sciences, 2021 Como medições não intrusivas de transmissão de raios gama, uma contribuição significativa para os modelos de estrutura de fluxo que descrevem o sistema FCC riser multifásico.
Victor Hugo Farias Ferreira da Silva +9 more
doaj +1 more source