Validation of the Serpent 2 code on TRIGA Mark II benchmark experiments

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Natural Sciences, Nuclear Engineering, Physics +13

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

M. B. Chadwick, P. Obložinský, M. Herman et al. · Nuclear Data Sheets · 2006 · 2.2K citations · Full text

Natural Sciences, Nuclear Engineering, Physics +14

The Serpent Monte Carlo code: Status, development and applications in 2013

Jaakko Leppänen, Maria Pusa, Tuomas Viitanen et al. · Annals of Nuclear Energy · 2014 · 1.4K citations

Engineering, Nuclear Engineering, Computational Physics +14

TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code

Emeric Brun, F. Damian, Cheikh M’Backé Diop et al. · Annals of Nuclear Energy · 2014 · 337 citations

Business, Nuclear Engineering, Nuclear Chemistry +9

Computational analysis of irradiation facilities at the JSI TRIGA reactor

Luka Snoj, Gašper Žerovnik, Andrej Trkov · Applied Radiation and Isotopes · 2011 · 253 citations

Engineering, Nuclear Engineering, Nuclear Physics +15