Results 221 to 230 of about 25,046 (241)

On normalization of fluxes and reaction rates in MCNP criticality calculations

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

Nuclear Data Activities Supporting MCNP [Slides]

Nuclear Criticality Safety Program (NCSP) Technical Program Review 2022, Held Virtually, Oak Ridge, TN (United States), 15-17 Feb 2022, 2022
Jeremy Conlin, Ryan Siggins, Colin Josey
openaire   +1 more source

Simulations of mass attenuation coefficients for shielding materials using the MCNP-X code

, 2017
H. O. Tekin, T. Manici
semanticscholar   +1 more source

Validation of absolute axial neutron flux distribution calculations with MCNP with 197Au(n,γ)198Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor

Applied Radiation and Isotopes, 2014
Vladimir Radulovic, Žiga Štancar, Luka Snoj   +2 more
exaly  

Comparative Study of Micro and Nano Size WO3/E44 Epoxy Composite as Gamma Radiation Shielding Using MCNP and Experiment

, 2017
S. Malekie, N. Hajiloo
semanticscholar   +1 more source

MCNP Slope Estimate Discussion

2006
openaire   +1 more source

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

Annals of Nuclear Energy, 2014
Wen-Xi Tian, Dalin Zhang, Yingwei Wu
exaly  

MCNP Clinic

openaire   +1 more source

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

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