This special issue focuses on the latest advancements in numerical methods dedicated to the analysis of neutronic-thermal hydraulic coupling in nuclear reactors. Neutronic-thermal hydraulic coupling plays a vital role in understanding reactor behavior and safety. Accurate and efficient numerical techniques are essential for capturing the complicated interaction between neutronics and thermal hydraulics, enabling realistic simulations and predictions. The special issue seeks contributions from researchers and experts actively involved in the development and application of advanced numerical methods for neutronic-thermal hydraulic coupling. It aims to provide a comprehensive overview of state-of-the-art approaches, their validation, and their impact on reactor analysis and design.

Topics of interest include:

(1)Innovative computational methods for simultaneous neutronic and thermal hydraulic equation solving.

(2)High-fidelity numerical schemes for accurate representation of neutronic and thermal hydraulic phenomena.

(3) Adaptive meshing strategies for complex geometries and transient behavior.

(4) Reduced-order modeling techniques for efficient neutronic-thermal hydraulic coupling analysis.

(5) Multiphysics solvers for simulating neutronic-thermal hydraulic feedback.

(6) Uncertainty quantification and sensitivity analysis methods for numerical predictions.

(7) Integration of numerical methods with optimization algorithms for reactor design.

(8) Verification and validation using experimental data and benchmark problems.

(9) Application of numerical methods to address neutronic-thermal hydraulic coupling challenges in existing and advanced reactor designs.

(10) Case studies showcasing the benefits and limitations of different numerical approaches.

We invite researchers and practitioners in the field of neutronic-thermal hydraulic coupling to submit their original research contributions. This special issue aims to facilitate knowledge exchange, stimulate discussions, and advance the field by highlighting the latest innovations in numerical methods for the analysis of neutronic-thermal hydraulic coupling in nuclear reactors.