Abstract
Graphite has been used in large volumes as a structural material and neutron moderator since the earliest days of nuclear fission. However, no international consensus exists on the disposal of irradiated graphite, leaving much of the historic radioactive graphite inventory in interim vault or silo storage. With several new graphite-moderated reactors planned or under construction, the issue of graphite waste management is becoming increasingly urgent. This paper reviews and quantifies impurities in both historic and modern nuclear graphite, with emphasis on nitrogen—responsible for much of the 14C inventory—and chlorine, which plays a critical role in repository performance and design. Modern graphites, benefitting from stringent quality-control measures developed for non-nuclear industries, meet or exceed the ASTM Ultra-High Purity nuclear standards, even without halide purification. Both chlorine and nitrogen concentrations have declined over time. For chlorine, identified as a key impurity influencing U.S. waste repository design, we propose a target of 0.1 appm in as-fabricated billets as a reasonable benchmark. Nitrogen sources are traced throughout the graphite production process, with surface and bulk concentrations characterized for all materials studied. Modern graphites commonly exhibit nitrogen levels below 5 appm, with values approaching 1 appm achievable. Using such reduced-nitrogen grades is critical to keeping graphite-induced radioactivity below the greater-than-Class-C waste threshold, thereby avoiding disposal cost penalties of nearly an order of magnitude.
| Original language | English |
|---|---|
| Article number | 101242 |
| Journal | Current Opinion in Solid State and Materials Science |
| Volume | 39 |
| DOIs | |
| State | Published - Dec 2025 |
Funding
The authors would like to thank Dr. Frank Goldner for contributing the National Carbon CP-1 reactor graphite for this study, and Professor Anthony Wickham for contributing the graphite used in the Hanford, Windscale, Magnox, and RBMK reactors. This work was sponsored by the Department of Energy, Office of Nuclear Energy under an Integrated Research Proposal grant: Reduction, Mitigation, and Disposal Strategies for the Graphite Waste of High Temperature Reactors. (DE-FOA-0002516 / IRP-22-27674). This work also benefitted from the use of the DOE Office of Science National Synchrotron Light Source accessed through competitive user proposal.
Keywords
- Chlorine
- Impurities
- Irradiation
- Nitrogen
- Nuclear graphite
- Nuclear waste