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Holtec submits partial construction permit application for SMRs at Palisades
On New Year’s Eve, Holtec International submitted Part 1 of a construction permit application to the Nuclear Regulatory Commission seeking a limited work authorization (LWA) to begin construction of a two-unit SMR-300 plant at the company’s site in Covert, Mich.
Named Pioneer-1 and -2, the twin 340-MWe pressurized water reactors would join the 777-MWe Palisades PWR that began operating in 1971, shut down in 2022, and is expected to reconnect to the grid—slightly delayed—early this year. According to Holtec’s application documents, Part 2 of its construction permit will be filed in no later than mid-2027.
Sara Bortot, Carlo Artioli, Marco E. Ricotti
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 329-337
Modeling and Simulations | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13441
Articles are hosted by Taylor and Francis Online.
A preliminary feasibility study and scope analysis for a demonstrator (demo) of the SUstainable Proliferation-resistance Enhanced Refined Secure Transportable Autonomous Reactor (SUPERSTAR) has been performed. Preliminary core design studies have been carried out focused on maximizing the power level compatibly with natural circulation cooling and transportability requirements, while meeting the foremost goals of (i) providing energy security and proliferation resistance thanks to a long life core design, (ii) minimizing the reactivity swing over the fuel lifetime, and (iii) flattening the radial power profiles, as demanded by the choice of wrapper-less fuel assemblies and by the stringent technological constraints imposed by the short-time-to-deployment feature. Once established appropriate geometrical pin and fuel assembly specifications, a suitable active height allowing the system to be cooled by free-flowing lead has finally been set through parametric T/H analyses. Fuel cycle calculations have been then performed to optimize both the fresh fuel composition and the radial enrichment zoning. Moreover, the use of several absorbing materials has been investigated in order to guarantee enhanced safety by incorporating control elements having a net density greater than that of the surrounding lead coolant. A complete static neutronic characterization of the resulting core has been finally accomplished.