New fuel materials to make nuclear reactors safer

The zirconium alloy cladding is highly reactive with water, especially the steam that can be produced if coolant water heats up under accident conditions. The steam causes it to oxidize and release the highly combustible gas hydrogen.

The main focus of Tonk’s work is to understand how the microstructure, or the small-scale structure of a material, impacts a material’s behavior. For these projects, he is looking at how the small-scale structures of potential new fuel and cladding materials will behave when exposed to reactor conditions, especially radiation.

“It’s well understood that the microstructure has a direct impact on the properties of the material, but my research focuses on harsh environments, where, because of the environment, the microstructure doesn’t stay static, but actually changes with time,” said Tonks. “It’s not enough just to design a microstructure that’s going to give you the behavior you want. You have to make sure that even as the microstructure evolves, it doesn’t ever result in behavior that’s going to cause your part or your reactor to fail.”

To understand these microstructures, Tonks uses computational models to create simulations on scales ranging from 1 to 10 microns, which is much smaller than a strand of hair. These simulations predict a material’s behavior under a variety of conditions.

Tonks and his research team are part of three projects that explore possible alternatives for a safer reactor fuel by using these simulations. In regards to the cladding, the simplest solution they are looking into is layering other materials over the zirconium alloy cladding. By creating layers of materials, researchers hope to get the strengths of the different metals and eliminate the weaknesses. The layered material would protect the cladding from reacting with steam and producing hydrogen. However, the layers could be more prone to radiation damage. Tonks is using modeling to simulate reactor conditions and understand the changes these materials experience.

The group is also exploring the feasibility of completely changing the cladding material to a silicon carbide composite. Silicon carbide has a lot of the same benefits of zirconium alloy and has been used in many non-nuclear applications. It has the added benefit of not reacting with coolant water, so it would not degrade and produce hydrogen inside the reactor. Unfortunately, the composite is hard to fabricate and it has the potential to crack. Tonks is using fracture simulations under normal and accident conditions to determine how radiation induces cracking and whether those microcracks would allow fission products to escape.

To address the thermal conductivity issues with reactor fuel, the research team is simulating various fuel additives to raise the thermal conductivity of the uranium dioxide. Tonks is focusing on determining the possible side effects of the various additives when used in a harsh reactor environment.

“Our role is developing the models for these systems,” Tonks said. “No one has ever done this before so there are no models. We are developing the models from scratch and then using them to help evaluate if these concepts are viable or not.”

Specifically the researchers are looking for potentially damaging interactions between the new materials and radiation in normal and accident operating conditions.

“We are hoping to be able to apply the tools that we have developed for understanding uranium dioxide and zirconium alloy, but now extend them to look at these new materials.”

One of the main tools that Tonks is using for these projects is a mesoscale fuel performance tool called MARMOT, which is being developed by the U.S. Nuclear Energy Advanced Modeling and Simulation Program. Tonks was the lead developer for MARMOT while at the Idaho National Laboratory.

The work by Tonks and his research team will help evaluate accident tolerant fuels faster than if researchers were using experimental data alone. Modeling provides data less expensively and more easily than running full nuclear tests. The simulations will guide the experimental work being completed by collaborators by pinpointing the fuels that are most likely to be viable so researchers can prioritize the experimental work.

Penn State notes that all of the accident tolerant fuels work is funded through the U.S. Department of Energy Nuclear Energy University Program. The silicon carbide work is a collaboration between University of Wisconsin-Madison and Penn State. The multi-layer composite cladding work is a collaboration between Ohio State, MIT, Penn State, Aalto University in Finland, and VTT Technical Research Centre in Finland. The work with fuel additives is a collaboration between MIT, University of Wisconsin-Madison, Texas A&M, Penn State, Idaho National Laboratory, AREVA, and ANATECH.