Adam Nelson

OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

Paul K. Romano, Benoit Forget, Kord Smith, 2014, ICS 2014.

The Effect of the Flux Separability Approximation on Multigroup Neutron Transport

P. Romano, William Boyd, Adam Nelson, 2021, Journal of Nuclear Engineering.

Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code

Paul K. Romano, Benoit Forget, Kord Smith, 2019, Nuclear Technology.

OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development

C. Calvin, Nicholas E. Horelik, Bryan R. Herman, 2014, ICS 2014.