A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT

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

Nuclear Data Library, Nuclear Energy, Nuclear Physics +7

The ERANOS Code and data system for fast reactor neutronic analyses

G. Rimpault, Danièle Plisson, J. Tommasi et al. · HAL (Le Centre pour la Communication Scientifique Directe) · 2002 · 247 citations · Full text

The Application of Reactor Kinetics to the Analysis of Experiments

A.F. Henry · Nuclear Science and Engineering · 1958 · 204 citations

Engineering, Fuel Science, Reactor Physics +17

Monte Carlo variance reduction with deterministic importance functions

Alireza Haghighat, John C. Wagner · Progress in Nuclear Energy · 2003 · 190 citations · Full text

A generalized perturbation method for bi-linear functionals of the real and adjoint neutron fluxes

A. Gandini · Journal of Nuclear Energy · 1967 · 163 citations

Numerical Analysis, Bi-linear Functionals, Nuclear Physics +12