Nuclear reactor physics and engineering

Advanced nuclear reactor physics sits at the intersection of fundamental particle interactions and large-scale engineering, tracing how neutrons are born, scatter, and are absorbed as they drive a self-sustaining chain reaction inside a reactor core. A new generation of reactor designs — including molten salt systems cooled by liquid fluoride or chloride salts, lead-cooled fast reactors, and thorium-fueled concepts — aims to improve safety margins, reduce long-lived radioactive waste through transmutation, and extract more energy from available fuel resources than conventional light-water designs allow. Accurate simulation is central to progress in this area, and researchers rely heavily on Monte Carlo transport codes paired with nuclear data libraries to model neutron behavior in geometrically complex, high-temperature environments where traditional analytical methods break down. Open questions include how to validate these simulations against experimental benchmarks at the precision needed for regulatory approval, and whether thorium fuel cycles can be made economically and proliferation-resistant enough to justify the infrastructure required to deploy them at scale.

Works

317,617

Total citations

570,175

Keywords

Nuclear ReactorMolten SaltNeutron TransportGeneration IVThorium Fuel CycleMonte Carlo Code