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Key research themes
1. How can nuclear reactor kinetics and control algorithms be optimized for load-following operation in pressurized water reactors?
This research theme investigates the modeling, control strategies, and operational limitations of nuclear reactors, particularly pressurized water reactors (PWRs), when adapting to fluctuating power demands. Load-following capability is increasingly important in systems integrating intermittent renewables, requiring reactors to adjust power output frequently while maintaining core stability and safety.
Key finding: This paper reviews various neutron transport models (single/multi-point kinetics, 1D diffusion) and advanced control algorithms (PID, LQG, MPC, neural networks) to manage reactor power and axial power distribution during... Read more
Key finding: This study demonstrates coupling a sensible heat thermal energy storage (TES) system to small modular reactors (SMRs) to enable steady-state reactor operation while decoupling electrical output from reactor power. By... Read more
Key finding: This comprehensive textbook underlines that understanding neutron physics—including kinetics, feedback effects, and power distribution—is fundamental to reactor control in load-following contexts. It stresses the interplay... Read more
2. What are the advancements in thermal-hydraulic modeling and fuel behavior analysis for research and advanced reactors during steady-state and transient conditions?
This theme focuses on computational modeling and experimental studies to analyze fuel behavior, thermal hydraulics, and safety margins under normal and accident conditions, including Reactivity-Initiated Accidents (RIA). Both steady-state and transient analyses provide critical insights supporting fuel design, reactor upgrades, and safety evaluations in research and liquid-metal reactors.
Key finding: This work extends the Pronghorn MOOSE-based subchannel thermal-hydraulics code to model liquid-metal reactors (LMRs), particularly sodium fast reactors with wire-wrapped fuel assemblies. It validates the code under normal and... Read more
Key finding: Applying coupled neutronic and thermal-hydraulic codes (MTR-DYN and EUREKA-2/RR), this paper provides improved modeling of the RSG-GAS research reactor under Reactivity-Initiated Accident conditions. It simulates control rod... Read more
Key finding: This study proposes a conceptual core upgrade for the Missouri S&T research reactor to extend operational power levels and flexibility. It couples neutronic analysis (using MCNP) and thermal-hydraulic simulations (via CFD) of... Read more
3. How can safety and aging be managed in research reactors through regulatory frameworks and operational monitoring?
This theme addresses regulatory requirements, safety management practices, and aging mitigation strategies tailored for the long-term operation and decommissioning of research reactor facilities. It encompasses aging management systems, radiation protection during abnormal fuel conditions, and documentation control to ensure compliance with national and international standards.
Key finding: This review clarifies that aging management for the Triga IPR-R1 research reactor in Brazil is guided by IAEA safety standards and international best practices due to gaps in national regulations. It underlines the need for... Read more
Key finding: The paper evaluates radiological protection measures undertaken following detection of fuel cladding failure in a TRIGA reactor, highlighting the correlation between cladding degradation, fission product release (notably... Read more
Key finding: The decommissioning of the TR Fusion Test Reactor (TFTR) exemplifies rigorous safety culture, operational planning, and novel tooling adapted to mitigate radiological hazards associated with tritium and activation products.... Read more