Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor

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

The molten salt reactor (MSR) in generation IV: Overview and perspectives

J. Serp, M. Allibert, O. Beneš et al. · Progress in Nuclear Energy · 2014 · 1.1K citations · Full text

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +13

OpenMC: A state-of-the-art Monte Carlo code for research and development

Paul Romano, Nicholas E. Horelik, Bryan Herman et al. · Annals of Nuclear Energy · 2014 · 1K citations · Full text

Computing, High-performance Computing, Nuclear Engineering +17

Expokit

Roger B. Sidje · ACM Transactions on Mathematical Software · 1998 · 802 citations · Full text

Computing, Computer Science, Computational Physics +11

A Technology Roadmap for Generation IV Nuclear Energy Systems

U.S. Doe · Medical Entomology and Zoology · 2002 · 677 citations

Engineering, Nuclear Engineering, Systems Engineering +14