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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.”
Ralf Wittmaack
Nuclear Technology | Volume 119 | Number 2 | August 1997 | Pages 158-180
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35384
Articles are hosted by Taylor and Francis Online.
New design features of future reactors are being developed to ensure the integrity of the reactors under severe accident conditions. These features include the spreading of corium with subsequent flooding and cooling. Numerical simulations are performed to reduce the number of necessary large-scale experiments with radioactive material. For this reason, the development, verification, and validation of simulation methods are important foci. A method for predicting three-dimensional free-surface flows of a single-component, incompressible Newtonian fluid is presented. The thermodynamics and discrete phase transitions are simulated also. In addition to the fluid, structural materials are considered as hydrodynamic obstacles and heat structures. The method is applied to several flow, heat transfer, and phase transition problems of water and glycerol and of cerrotru (low-melting Bi-Sn alloy), thermite, and corium melts. The predictions provide a satisfactory representation of the experimental data and analytical solutions. Different physical processes are analyzed, e.g., gravity waves, creeping flows, Bénard convection, and thermodynamic interactions of fluid, structural material, and surroundings. The method is applied to the layout and design of experiments and exvessel corium-retention devices in nuclear reactors.