Post-irradiation examination of the Sirius-1 nuclear thermal propulsion fuel test

• Published in: Acta astronautica Vol. 212; no. C; pp. 187 - 197
• Main Authors: Schulthess, Jason, Pu, Xiaofei, Petersen, Philip, Burns, Jatuporn, Jerred, Nathan, Fleming, Austin, Craft, Aaron, Chuirazzi, William, Woolstenhulme, Nicolas, O'Brien, Robert
• Format: Journal Article
• Language: English
• Published: United Kingdom Elsevier Ltd 01.11.2023; Elsevier
• Subjects: Cermet; Nuclear fuel; Nuclear thermal propulsion; Post-irradiation examination; Transient test; TREAT; Transient test; Nuclear fuel; TREAT; Post-irradiation examination; Nuclear thermal propulsion; Cermet
• ISSN: 0094-5765; 1879-2030
• DOI: 10.1016/j.actaastro.2023.07.044

Nuclear Thermal Propulsion (NTP) systems hold promise in reducing transit times for exploration of the solar system by both crewed and uncrewed missions. NTP systems currently under investigation include a once-through high-temperature gas-cooled fission reactor to provide thermal energy to heat the coolant, which also serves as the propellant. The fuel system consists of angular UN fuel particles dispersed in a matrix of W/Re, creating a ceramic and metallic composite or cermet, which has been irradiated in Idaho National Laboratory's (INL) Transient Reactor Test Facility (TREAT). This enabled evaluation of these materials under representative nuclear heating rates (∼95 K/s) and peak surface temperatures (∼2527 K). These surface conditions were indicative of achievement of the target peak internal temperature of approximately 2850 K. These tests named Sirius-1 (UN–W/Re), have been irradiated and this paper will present post-irradiation examination results. The Sirius-1 test produced minor, stable cracks in the fuel specimen and spalling of surface material. Volatilized uranium ‘soot’ was found deposited on the inner wall of the irradiation capsule indicating loss of some fissile material from the fuel specimen. Spalling from the surfaces was also noted upon visual inspection. Uranium diffusion from the fuel particles resulted in the formation of U/Re phases and the production of a laminar microstructure on the edge of the fuel system. Overall, the specimen was stable and remained within a coolable geometry upon conclusion of multiple thermal cycles to prototypical operating temperatures. •A cermet nuclear fuel of UN particles in a W/Re matrix was irradiated and examined.•The sample material is a candidate for a nuclear thermal propulsion system.•The irradiation used prototypic heating rates and peak temperatures.•Post examination revealed that the fuel specimen remained largely intact.•Some localized zones of intermetallic W–Re sigma phase existed.