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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
C. W. Hunter, R. L. Fish, J. J. Holmes
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 376-388
Department | Fuel | doi.org/10.13182/NT75-A24311
Articles are hosted by Taylor and Francis Online.
Internally pressurized specimens of unirradiated 20% cold-worked Type 316 stainless-steel cladding were rapidly heated and burst to determine mechanical behavior under various simulated reactor transient events. The tests were conducted at heating rates of 10 and 200 F°/sec. Failure temperatures from 500 to 2500°F were obtained, with the principal emphasis on the behavior above 1000°F. Failure temperatures increased with decreasing internal pressure while cladding ductility initially increased with increasing failure temperature, but above ∼2100°F the ductility decreased steadily with increasing temperature. The increase in ductility with increasing temperature was due to recovery and recrystallization of the cold-worked material, while the decrease above 2100°F resulted from grain growth. The diametral failure strains were between 0.5 to 1.0% at 1000°F. The maximum diametral failure strain values reached 8% for the 10 F°/sec ramp and 4% for the 200 F°/ sec ramp at the elevated temperatures.