Results 191 to 200 of about 16,330 (259)

MCNP geometry transformation and plotter equations

Progress in Nuclear Energy, 2012
Abstract The MCNP Monte Carlo radiation-transport code contains versatile capabilities to develop and plot geometries used in simulations. Although these capabilities have been available in MCNP since the late 1970s, many of the derivational details underpinning these capabilities are not contained in the MCNP manual and do not appear to have been ...
Joe W Durkee
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

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

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

, 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 ...
Ö. Akcali, M. Caglar, Ozan Toker, Bayram Bilmez, H. B. Kavanoz, O. İçelli   +5 more
semanticscholar   +1 more source

The comparison of MCNP perturbation technique with MCNP difference method in critical calculation

Nuclear Engineering and Design, 2010
Abstract For a nuclear fission system, we calculated Δkeff, which arise from system material composition changes, by two different approaches, the MCNP perturbation technique and the MCNP difference method. For every material composition change, we made four different runs, each run with different cycles or each cycle generating different neutrons ...
Bin Liu, Xuefeng Lv, Wei Zhao, Kai Wang, Jing Tu, Xiaoping Ouyang   +5 more
openaire   +1 more source

Application of the MCNP 5 code to simulate the shielding features of concrete samples with different aggregates

, 2020
The gamma ray attenuation parameters for three different series of concretes containing different ratios of basalt, magnetite, and bismite mineral aggregates were studied using the Monte Carlo simulation MCNP 5 code.
M. Sayyed, K. Mahmoud, Sazirul Islam, O. Tashlykov, E. Lacomme, Kawa M. Kaky   +5 more
semanticscholar   +1 more source

Validation of two calculation options built in Elekta Monaco Monte Carlo based algorithm using MCNP code

, 2021
Introduction The calculation algorithm for intensity modulated radiotherapy (IMRT) built in the Elekta Monaco treatment planning system (TPS) is based on Monte Carlo (MC) simulation. Absorbed dose is calculated as dose to medium in medium (Dm,m), but the
Manda Švabić Kolacio, H. Brkić, D. Faj, Đ. Radojčić, D. Rajlić, N. Obajdin, S. Jurković   +6 more
semanticscholar   +1 more source

Investigation of gamma-ray shielding capability of glasses doped with Y, Gd, Nd, Pr and Dy rare earth using MCNP-5 code

, 2020
The capability of using five rare earth oxides (Y2O3 (S1-Y), Gd2O3 (S2-Gd), NdCl3 (S3-Nd), PrO11 (S4-Pr), and Dy2O3 (S5-Dy)) doped glasses as gamma-rays shielding has been evaluated. The mass attenuation coefficient (MAC, μm) in the photon energy between
K. Mahmoud, Y. Rammah
semanticscholar   +1 more source

MCNP Monte Carlo: a precis of MCNP

SPIE Proceedings, 1997
MCNPTM Monte Carlo: a precis of MCNPKenneth J. AdamsTransport Methods Group, XTM MS B226Los Alamos National Laboratory, Los Alamos, NM, 87545ABSTRACTMCNPTM* is a general purpose tiiree-dimensional time-dependent neutron, photon, and electron transport code.
openaire   +1 more source

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

Progress in nuclear energy (New series), 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, H. Tavakoli-Anbaran
semanticscholar   +1 more source