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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.
Bei Ye, Jeff Rest, Yeon Soo Kim, Gerard Hofman, Benoit Dionne
Nuclear Technology | Volume 191 | Number 1 | July 2015 | Pages 27-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-56
Articles are hosted by Taylor and Francis Online.
DART (Dispersion Analysis Research Tool) is a computational code developed for integrated simulation of the irradiation behavior of aluminum dispersion fuels used in research reactors. The DART computational code uses a mechanistic fission gas behavior model and a set of up-to-date empirical correlations to simulate the fuel morphology change as a function of burnup. Integrating a thermal calculation subroutine enables fuel material properties to be updated at each time step. This paper describes the primary physical models that form the basis of the DART computational code. A baseline validation was performed through the modeling of several U-Mo/Al mini-plate tests (RERTR-6, 7, and 9) in the Advanced Test Reactor (ATR). A demonstration problem is also presented through the calculation of fuel plate swelling and constituent volume fractions in full-sized plates from the AFIP-1 test in ATR.