Results 101 to 110 of about 10,040 (154)

Assessment of different MCNP Monte Carlo codes in electron absorbed dose

Reports of Practical Oncology & Radiotherapy, 2006
SummaryBackgroundMCNP is a general-purpose Monte Carlo code for simulation of neutrons, photons and electrons or coupled neutron/photon/electron transport. This code is based on ETRAN/ITS codes. There are different versions of this code.AimThis work aims to compare the more recently released MCNP codes with the earlier version in terms of the central ...
Ali Nedaie, Hassan, Mosleh-Shirazi, M.A., Gharaati, H., Shariari, M., Allahverdi, M.   +4 more
openaire   +1 more source

The multigroup library processing method for coupled neutron and photon heating calculation of fast reactor

Nuclear Engineering and Technology
To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups.
Teng Zhang, Xubo Ma, Kui Hu, GuanQun Jia
doaj   +1 more source

Comparison of three methods of calculation, experimental and monte carlo simulation in investigation of organ doses (thyroid, sternum, cervical vertebra) in radioiodine therapy

Journal of Medical Signals and Sensors, 2012
Radioiodine therapy is an effective method for treating thyroid cancer carcinoma, but it has some affects on normal tissues, hence dosimetry of vital organs is important to weigh the risks and benefits of this method.
Daryoush Shahbazi-Gahrouei, Saba Ayat
doaj  

The MCNP Code: 6.3 and Beyond [Slides]

, 2022
Colin Josey, Joel Kulesza, Michael Rising   +2 more
openaire   +2 more sources

Design and Evaluation of Nanoparticle-Reinforced Glass for Radiation Shielding in Angiography: An MCNP Simulation Study

Journal of Advanced Research in Natural and Applied Sciences
Angiography is a widely utilized diagnostic and treatment method involving relatively high radiation doses for patients and personnel. Protecting radiation-sensitive organs, such as the eye lens, is crucial in this imaging modality.
Navid Kheradmand, Mustafa Çağlar
doaj   +1 more source

Code Verification for MCNP Unstructured Mesh Geometry

, 2020
Harrison Leiendecker, Alex Warhover, Jerawan Armstrong, Jim Ferguson   +3 more
openaire   +2 more sources

Experimental and theoretical study on the physico-mechanical characteristics and radiation shielding capability of hardened alumina sludge waste-cement pastes containing MnFe2O4-nanoparticles

Discover Applied Sciences
This research investigates the impact of incorporating low-cost MnFe2O4 spinel nanoparticles (MF-NPs) at varying concentrations (0.5, 1, and 2 mass%) on the mechanical and physical properties of blended cement pastes.
Amal A. El-Sawy, Mohamed Heikal, Sahar M. Ibrahim, O. A. Mohamed   +3 more
doaj   +1 more source

CREPT-MCNP 1.1 (Calibration Code for the Representative Point Method with MCNP); User manual, Version 1.1.0

CREPT-MCNP 1.1 (Calibration Code for the Representative Point Method with MCNP); User manual, Version 1.1.0
The representative point method is a novel method which enables efficiency calibrations with a standard point source. A calculation code for implementing the method has been developed. The code is named CREPT-MCNP (\(\underline{C}\)alibration Code for the \(\underline{Re}\)presentative \(\underline{P}\)oin\(\underline{t}\) Method with MCNP).
openaire  

MatMCNP: A Code for Producing Material Cards for MCNP

, 2014
Kendall DePriest, Karen Saavedra
openaire   +2 more sources

MCNP(R) Particle Transport Code: Its History and Future [Slides]

, 2021
openaire   +2 more sources