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Return of the HB Line at SRS
The Department of Energy is bringing the HB Line facility at the Savannah River Site back on line to recycle surplus plutonium and produce uranium-plutonium mixed oxide (MOX) fuel for advanced reactors.
Restarting the facility will be a multiyear process and will yield opportunities for increased domestic production of isotopes with scientific and commercial value. The DOE said that once operational, the HB Line will accelerate the Office of Environmental Management’s plutonium disposition mission by 10 to 13 years while reducing the existing cost.
Pramatha Bhat, Kendall R. Adams, Stephen J. Herring, Brad Kirkwood
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 790-806
Research Article | doi.org/10.1080/00295450.2024.2361185
Articles are hosted by Taylor and Francis Online.
For deep-space propulsion and interplanetary exploration, the centrifugal nuclear thermal rocket (CNTR) has the ability to achieve a very high specific impulse (Isp) metric beyond that of conventional chemical rockets or solid-core nuclear thermal propulsion systems. The high Isp allows the rocket to use less propellant or achieve a higher velocity for shorter transit times. However, the cylindrical containment structure of a CNTR fuel element encounters extreme conditions, as it houses molten uranium at temperatures exceeding 1408 K, leading to challenges such as dissolution, chemical reactions, and thermal stresses that conventional materials struggle to withstand.
This study aims to address this issue by analyzing appropriate materials for constructing the cylindrical containment component. The operating conditions of the annular porous medium that confines the liquid uranium in the centrifugal fuel element are simulated by conducting a comprehensive one-dimensional numerical analysis using a range of candidate porous materials, including Mo, W, zirconium carbide, and silicon carbide. The porous structure facilitates the flow of the hydrogen propellant into the internal molten uranium section, where it gains significant thermal energy while simultaneously cooling the cylinder. The containment cylinder has an internal temperature of 1478.1 K, exceeding the melting point of uranium, while the external gas temperature of the hydrogen propellant is much lower. This temperature difference induces significant thermal stresses in the cylinder.
The porous containment cylinder made from molybdenum was able to maintain elastic deformation throughout the thickness of the cylinder, showcasing its ability to handle these extreme thermal stress conditions. Tungsten, on the other hand, experienced plastic deformation at the cylinder’s edges and elastic deformation through the middle radial locations. In contrast, the stresses experienced by the ceramic materials far exceeded their failure stress values, leading to brittle failure. These findings will help with the refinement of the CNTR design, edging it closer to practical implementation.