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Nuclear Science

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Nuclear Science

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Research Frontiers in Advanced Reactor Physics and Neutron Transport

Development of computational methods for solving neutron transport equations in next-generation reactor designs with improved accuracy and efficiency.

Neutron-Induced Transmutation Cascades in Fast Spectrum Environments

Anisotropic Scattering Effects in Heterogeneous Fuel Geometries

Burnup-Dependent Cross-Section Evolution and Feedback Mechanisms

Transport-Diffusion Coupling at Material Interfaces and Boundaries

Prompt Neutron Multiplication in Subcritical Driven Systems

Spectral Hardening in Ultra-Dense Reactor Cores

Delayed Neutron Precursor Transport and Kinetic Instabilities

Resonance Self-Shielding in Complex Lattice Structures

Neutron Leakage and Streaming Through Geometric Heterogeneities

Multiscale Coupling Between Microscopic Cross-Sections and Macroscopic Flux

All Nuclear Science PhD categories