Results 181 to 190 of about 25,046 (241)

Evaluation of photon shielding properties for new refractory tantalum-rich sulfides Ta9(XS3)2 alloys: A study with the MCNP-5

Annals of Nuclear Energy, 2023
M. Hamad
exaly   +2 more sources

Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code

Nuclear Engineering and Technology, 2019
The mass attenuation coefficient μ m for eight rock samples having different chemical composition was simulated using the MCNP 5 code in energy range ( 0.002 MeV ≤ E ≤ 10 MeV ) .
K G Mahmoud, M I Sayyed, Oleg L Tashlykov   +2 more
exaly   +2 more sources

Gamma Ray Shielding Study of Barium–Bismuth–Borosilicate Glasses as Transparent Shielding Materials using MCNP-4C Code, XCOM Program, and Available Experimental Data

Nuclear Engineering and Technology, 2017
In this work, linear and mass attenuation coefficients, effective atomic number and electron density, mean free paths, and half value layer and 10 th value layer values of barium–bismuth–borosilicate glasses were obtained for 662 keV, 1,173 keV, and 1 ...
Reza Bagheri, Alireza Khorrami Moghaddam, Hassan Yousefnia   +2 more
exaly   +2 more sources

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

Physica medica (Testo stampato), 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 ...
J. Šolc, J. Jakubek, L. Marek, C. Oancea, J. Pivec, J. Šmoldasová, J. Tesař, Z. Vykydal   +7 more
semanticscholar   +1 more source

Na2Si3O7/Ag micro and nano-structured glassy composites: The experimental and MCNP simulation surveys of their radiation shielding performances

Progress in Nuclear Energy, 2021
Mustafa çağlar, YaŞar Karabul, Mehmet KiliÇ   +2 more
exaly   +2 more sources

A new methodology to estimate stochastic uncertainty of MCNP-predicted isotope concentrations in nuclear fuel burnup simulations

Annals of Nuclear Energy, 2021
The Monte Carlo N-particle radiation transport code (MCNP) is used widely in nuclear fuel burnup simulation (FBS). In the FBS, MCNP predicts various neutron reaction rates and the associated stochastic relative error (SRE).
Sunil S Chirayath
exaly   +2 more sources

An investigation on gamma-ray shielding properties of quaternary glassy composite (Na2Si3O7/Bi2O3/ B2O3/Sb2O3) by BXCOM and MCNP 6.2 code

Progress in Nuclear Energy, 2020
Analytic and stochastic methods were proposed for the determination of gamma-ray radiation shielding properties of the glassy composites. Radiation shielding properties such as mass attenuation coefficients, effective atomic numbers, effective electron ...
Mustafa çağlar, OZAN TOKER, Bayram Bilmez   +2 more
exaly   +2 more sources

Study on gamma shielding polymer composites reinforced with different sizes and proportions of tungsten particles using MCNP code

Progress in Nuclear Energy, 2019
Metal polymer composites (MPCs) are new category of advanced materials whose effectiveness in the field of radiation protection has been confirmed experimentally and theoretically. By using MCNP code, this paper describes a modified model to study effect
Hoda Alavian, Hossein Tavakoli-Anbaran
exaly   +2 more sources

Comparison between MCNP and planning system in brachytherapy of cervical cancer.

Applied Radiation and Isotopes, 2022
Absorbed doses in uterus during brachytherapy were calculated with MCNP in relevant points and compared with planning system for one patients. MCNP was applied with two different humanoid phantoms in input, ORNL and voxel models, which represent human ...
D. Krstić, D. Nikezic, M. Jeremic, E. Dolićanin, T. Miladinović, Milena Živković   +5 more
semanticscholar   +1 more source

MCNP™ Version 5

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2004
Abstract The Monte Carlo transport workhorse, MCNP [Los Alamos National Laboratory report LA-13709-M, 2000], is undergoing a massive renovation at Los Alamos National Laboratory (LANL) in support of the Eolus Project of the Advanced Simulation and Computing (ASCI) Program.
R.Arthur Forster, Lawrence J Cox, Richard F Barrett, Thomas E Booth, Judith F Briesmeister, Forrest B Brown, Jeffrey S Bull, Gregg C Geisler, John T Goorley, Russell D Mosteller, Susan E Post, Richard E Prael, Elizabeth C Selcow, Avneet Sood   +13 more
openaire   +1 more source