Concepedia

Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems

Nicholas R. Brown, Jeffrey J. Powers, Bo Feng, F. Heidet, Nicolas Stauff, G. Zhang, M. Todosow, Andrew Worrall, Jess C Gehin, T. K. Kim,

Nuclear Engineering and Design · 2015 · 39 citations · 22 references

Open access

Concepts

EngineeringNuclear EngineeringPhysicsNuclear Fuel CycleNuclear MaterialsNuclear PhysicsNeutron Spectrum AnalysisNuclear FissionNuclear Fuel MaterialsRadioactive DecayReactor Core DesignThorium Fuel CycleFast Neutron SpectraFuel Utilization In Thorium CyclesThorium FuelThorium Fuel BurnupThorium-based Fuels

References

22

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

Molten Fluorides as Power Reactor Fuels

R. C. Briant, Alvin M. Weinberg · Nuclear Science and Engineering · 1957 · 114 citations

Engineering, Nuclear Engineering, Heat Transfer +15

The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor

E.S. Bettis, R.C. Robertson · Nuclear Applications and Technology · 1970 · 99 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +16