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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
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.