Analysis Of Autonomous Load Following (ALF) In Advanced Fast Reactors
Abstract
The autonomous load following (ALF) properties of fast-spectrum nuclear reactors offer great potential for increased electric grid stability, reduction in control rod mechanism wear, and less operator action for small power transients experienced on a daily basis. These features can result in design simplification and enhanced safety of such reactor systems. Thermal-hydraulic transients result in reactivity feedback from the coolant to curb power transients and return the reactor to a stable, critical condition. The speed of the reactivity feedback and the resulting limits on how large a transient can be controlled through autonomous load following are based to a great extent on the intrinsic properties of the coolant and its effects on the associated reactor kinetics. Lead, lead bismuth eutectic (LBE), and sodium are coolants that have properties amenable to ALF, and these primary coolant types are among the promising options for advanced fast reactors under the Generation IV program. This paper reviews the relevant properties of each coolant type and presents the heat-transfer modeling results of analyses using evaluated nuclear data files (ENDF) data and MATLAB to simulate their respective reactivity responses for a simplified fast reactor design. The results provide insight into comparison of coolant types based on reactivity feedback and autonomous load following capability in future fast reactor designs.
Document Details
- Document Type
- Technical Report
- Publication Date
- Dec 01, 2018
- Accession Number
- AD1069627
Entities
People
- Brad W. Kinnamon
Organizations
- Naval Postgraduate School