Results 241 to 250 of about 16,330 (259)

Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment

Annals of Nuclear Energy, 2014
Wenxi Tian, Hongyang Wei, Dalin Zhang
exaly  

Element analysis and calculation of the attenuation coefficients for gold, bronze and water matrixes using MCNP, WinXCom and experimental data

Radiation Physics and Chemistry, 2014
Seyed Pezhman Shirmardi, M E Medhat
exaly  

Thorium-Based Mixed Oxide Fuel in a Pressurized Water Reactor: A Burnup Analysis with MCNP

, 2018
L. P. Tucker, S. Usman
semanticscholar   +1 more source

Comparative studies on shielding properties of some steel alloys using Geant4, MCNP, WinXCOM and experimental results

Radiation Physics and Chemistry, 2015
Vishwanath P Singh, M E Medhat, Seyed Pezhman Shirmardi   +2 more
exaly  

An approach to design a 90Sr radioisotope thermoelectric generator using analytical and Monte Carlo methods with ANSYS, COMSOL, and MCNP.

Applied Radiation and Isotopes, 2017
Abolhasan Khajepour, F. Rahmani
semanticscholar   +1 more source

Analysis of JSI TRIGA MARK II reactor physical parameters calculated with TRIPOLI and MCNP

Applied Radiation and Isotopes, 2015
R Henry, Luka Snoj
exaly  

Gamma-ray shielding study of light to heavyweight concretes using MCNP-4C code

Nuclear Science and Techniques/Hewuli, 2016
Reza Bagheri, Alireza Khorrami Moghaddam   +1 more
exaly  

MCNP Clinic

openaire   +1 more source

MCNP modelling of scintillation-detector γ-ray spectra from natural radionuclides

Applied Radiation and Isotopes, 2002
M Maučec, R J De Meijer
exaly  

FENDL/A-MCNP and FENDL/A-VITJ_E

1996
openaire   +1 more source