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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.
J. M. Steichen
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 308-315
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31196
Articles are hosted by Taylor and Francis Online.
High strain rate tensile data have been obtained on Type 304 stainless steel which was irradiated in EBR-II to a maximum fluence of 0.7 × 1022 n/cm2 (E > 0.1 MeV) at a temperature of ∼950°F. Tests were performed over a range of strain rates from 3 × 10−5 to 1 × 101 sec−1 at 800 and 1000°F to provide mechanical properties information for safety analyses for the Fast Flux Test Facility. The results of these tests demonstrate that the strength of irradiated Type 304 stainless steel remains essentially constant with increasing strain rate and the ductility decreases with strain rate at a fluence of 0.2 × 1022 n/cm2 and increases with strain rate at a fluence of 0.7 × 1022 n/cm2.