Nuclear reactor physics and engineering
Advanced nuclear reactor physics sits at the intersection of quantum-scale neutron behavior and large-scale engineering systems, asking how fission chain reactions can be sustained, controlled, and made safe enough for practical power generation. Researchers working on Generation IV designs—such as molten salt reactors and lead-cooled fast reactors—are trying to move beyond the light-water technology that dominates today's fleet, seeking higher thermal efficiency, passive safety features, and the ability to consume long-lived radioactive waste through transmutation. The thorium fuel cycle has attracted renewed attention as an alternative to uranium, potentially offering greater fuel abundance and reduced proliferation risk, though converting that promise into reliable reactor performance requires solving hard problems in neutronics, materials compatibility, and fuel processing chemistry. Monte Carlo transport codes are central to this work, letting physicists simulate how neutrons travel and interact inside complex geometries, but improving their accuracy depends on nuclear data libraries that still carry meaningful uncertainties at energies relevant to fast-spectrum designs.
- Works
- 318,643
- Total citations
- 575,222
- Keywords
- Nuclear ReactorMolten SaltNeutron TransportGeneration IVThorium Fuel CycleMonte Carlo Code
Top papers in Nuclear reactor physics and engineering
Ordered by total citation count.
- Geant4—a simulation toolkit↗ 24,457OA
- Numerical Heat Transfer and Fluid Flow↗ 15,203
- MCNP-A General Monte Carlo N-Particle Transport Code↗ 5,126
- Review of particle properties↗ 4,421
- The Kolmogorov-Smirnov Test for Goodness of Fit↗ 3,713
- ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data↗ 2,812
- R-Matrix Theory of Nuclear Reactions↗ 2,581
- Materials challenges in nuclear energy↗ 2,558
- FLUKA: A Multi-Particle Transport Code↗ 2,517OA
- Transport Phenomena in a Completely Ionized Gas↗ 2,252
- ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data↗ 2,231OA
- ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology↗ 2,196OA
Active researchers
Top authors in this area, ranked by h-index.