Results 151 to 160 of about 2,294 (180)

Using MCNP for fusion neutronics: Dissertation

2008
Any fusion reactor using tritium-deuterium fusion will be a prolific source of 14 MeV neutrons. In fact, 80% of the fusion energy will be carried away by these neutrons. Thus it is essential to calculate what will happen to them, so that such quantities as the tritium breeding ratio, the neutron wall loading, heat deposition, various kinds of material ...
openaire   +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
Sunil Chirayath
exaly  

Comparison between MCNP and planning system in brachytherapy of cervical cancer

Applied Radiation and Isotopes, 2023
Dragoslav Nikezic, Dragana Krstić, Tatjana B Miladinovic   +2 more
exaly  

Evaluation of Radiation Shielding Features of Co and Ni-Based Superalloys Using MCNP-5 Code: Potential Use in Nuclear Safety

Applied Sciences (Switzerland), 2020
Karem Mahmoud, Eloic Lacomme, Kawa M Kaky   +2 more
exaly  

MCNP Developments [Slides]

ANS Winter Meeting 2011, Washington, DC (United States), 30 Oct - 3 Nov 2011, 2011
Forrest Brown, Brian Kiedrowski
openaire   +1 more source

Advances in MCNP for Reactor Calculations

Transactions of the American Nuclear Society - Volume 122, 2020
R. Wilkerson, G. McKinney, C. Josey, M. Blood, J. Galloway, J. Armstrong, H. Trellue   +6 more
openaire   +1 more source

Validation of DT source term modelling in MCNP and MCUNED codes against SINBAD fusion benchmarks

Fusion Engineering and Design, 2020
Aljaz Cufar
exaly  

Use of McCad for the conversion of ITER CAD data to MCNP geometry

Fusion Engineering and Design, 2008
Arkady Serikov
exaly  

MCNP geometry transformation and plotter equations

Progress in Nuclear Energy, 2012
Joe W Durkee
exaly  

On normalization of fluxes and reaction rates in MCNP criticality calculations

Annals of Nuclear Energy, 2014
Gasper Žerovnik, Luka Snoj
exaly