Krishna Pillai, professor of mechanical engineering, has received funding from the U.S. Department of Energy’s Idaho National Laboratory (INL) to advance the modeling of oxidation and degradation in porous graphite—an essential material used in certain nuclear reactor components.
As the demand for energy-intensive data centers grows, especially with the rise of artificial intelligence companies, there is renewed interest in nuclear power as a reliable, large-scale energy source.
INL is at the forefront of developing these advanced reactors which are being designed smaller than their predecessors. The compact size of these next-gen reactors (called high temperature gas-cooled reactors) aims to improve safety, cooling efficiency, and cost-effectiveness.
Core components of the reactors are made of graphite which sustains atomic fission in a controlled manner, reflects heat, and protects the reactor’s internal structure.
However, graphite is susceptible to oxidation which reduces its benefits.
So, being able to predict the potential for oxidation is also what INL researchers are focused on.
Pillai’s contribution
Before accurate simulations can be created, INL has enlisted Pillai to complete the first step. His role is to develop mathematical models that will help scientists run simulations to estimate how fast the graphite will wear out, how much weaker it gets, and how long it will last in a reactor.
By applying advanced engineering mathematics – specifically, the volume averaging method – Pillai will be able to predict what happens to the tiny pores inside the graphite when it’s exposed to the heat and conditions inside a reactor. These small-scale changes are hard to see directly, so he’s using advanced math to describe the overall behavior of the material with a few equations instead of trying to track every tiny detail.
“My work with INL scientists will result in accurate mathematical models that can be used for predictive simulations,” he said, “helping them better understand and have advance warning of graphite degradation in high-temperature reactors.”
Pillai’s equations also will help INL scientists as they develop a graphite degradation modeling tool. The tool will help engineers assess the reliability of graphite components using industry-standard design codes.
These insights will enable researchers and engineers to optimize reactor designs, improve maintenance, and ensure that nuclear energy can offer a safe option for powering the data-driven future.