Results 31 to 40 of about 4,292 (208)

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, M. B. Chadwick, R. K. Corzine, H. W. Egdorf, F. X. Gallmeier, R. C. Little, R. E. MacFarlane, S. G. Mashnik, E. J. Pitcher, R. E. Prael, A. J. Sierk, E. C. Snow, L. S. Waters, M. C. White, P. G. Young   +14 more
openaire   +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, Kheradmand Saadi Mohsen, Athari Allaf Mitra   +2 more
doaj   +1 more source

Cálculo, usando o código MCNPX, de doses equivalentes no tratamento 3D-CRT de câncer de próstata, com gantry operando a 45°, 135°, 225° e 315°

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, Claudio Oliveira, Wilson Rebello, Marcos Paulo Medeiros, Clóves Fonseca, Camila Baptista   +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

Determination of fluid dynamic parameters through imports of CFD images validated in experiments for the MCNPX code.

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, Carlos Costa Dantas, Silvio de Barros Melo, Fernando Roberto de Andrade Lima, Pamalla Rafaelly Barbosa de Oliveira, Tennyson Accetti Resende Filho, Jorge Alexandre Gomes Lins, Eudes Bertony Vieira, Bruno Gomes Andrade, Milton Santos Viana   +9 more
doaj   +1 more source

Improved organ absorbed dose estimation in abdominal CT using DICOM header-based tube current modulation profiles: Validation with measurements and Monte Carlo simulations. [PDF]

J Appl Clin Med Phys
Abstract Purpose Precise determination of organ absorbed doses in computed tomography (CT) is vital for evaluating radiation risk and optimizing radiation dose. This study aimed to improve the accuracy of organ absorbed dose estimates in abdominal CT by integrating tube current modulation (TCM) profiles—extracted from the Digital Imaging and ...
Nuntue C, Matsubara K, Watanabe S, Fukushima K, Tantiwetchayanon K.   +4 more
europepmc   +2 more sources

Determination of gamma-ray transmission factors of WO3–TeO2–B2O3 glasses using MCNPX Monte Carlo code for shielding and protection purposes

Applied Rheology, 2022
The aim of this study is to assess the individual gamma-ray transmission factors (TFs) and some fundamental gamma-ray attenuation properties of several types of glasses based on WO3–TeO2–B2O3 glasses system.
ALMisned Ghada, Sen Baykal Duygu, Susoy Gulfem, Kilic Gokhan, Zakaly Hesham M. H., Ene Antoaneta, Tekin Huseyin Ozan   +6 more
doaj   +1 more source

Neutronic Evaluation of MSBR System Using MCNP Code

Brazilian Journal of Radiation Sciences, 2021
The concept of Molten Salt Reactor use Th to breed fissile 233U, where an initial source of fissile material needs to be provided. However, there is no available 233U and so; the fissile fuel supply is one of the unresolved problems.
Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira   +3 more
doaj   +1 more source

Validation and study of different parameters in the simulation of diagnostic X-ray spectra using the MCNPX code

Brazilian Journal of Radiation Sciences, 2023
In radiology, knowing the X-ray spectrum characteristics makes it possible to estimate the absorbed dose in the patient and to improve image quality. In this study, an X-ray generator was proposed using the MCNPX code and to validate it, the simulated ...
K.C.W. Consatti, W. S. Santos, J. V. B. Valença, M. T. Yoshizumi   +3 more
doaj   +1 more source

Characterization of the light and flexible nonlead aprons as an alternative to Pb-PVC. [PDF]

J Appl Clin Med Phys
Abstract Background Radiation shielding is crucial for protecting healthcare professionals from scatter radiation during x‐ray procedures. Conventional lead aprons, although effective, are limited by their high weight, low flexibility, and potential toxicity.
Khorami MT, Salehi Z.
europepmc   +2 more sources