1. Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh. (3rd July 2021) Authors: Gaston, Derek R.; Forget, Benoit; Smith, Kord S.; Harbour, Logan H.; Ridley, Gavin K.; Giudicelli, Guillaume G. Journal: Nuclear technology Issue: Volume 207:Number 7(2021) Page Start: 931 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗
2. Multigroup Cross-Section Generation with the OpenMC Monte Carlo Particle Transport Code. (3rd July 2019) Authors: Boyd, William; Nelson, Adam; Romano, Paul K.; Shaner, Samuel; Forget, Benoit; Smith, Kord Journal: Nuclear technology Issue: Volume 205:Number 7(2019) Page Start: 928 Record Type: Journal Article View Content: Available online (eLD content is only available in our Reading Rooms) ↗