SCWRSSt. Croix Watershed Research Station (Science Museum of Minnesota)
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References in periodicals archive ?
The work carried out in this study presents the first reactivity initiated accidents for the Canadian SCWR. Given the importance of RIA in the literature review of the HPLWR, it is important that such accidents be analyzed for the Canadian design.
This section presents the reactor physics and thermal hydraulics models built to simulate the Canadian SCWR.
The fuel channel geometry and materials specifications for the Canadian SCWR lattice are summarized in Table 1.
Hummel et al., "A Benchmark Comparison of the Canadian Supercritical Water-cooled Reactor (SCWR) 64-element Fuel Lattice Cell Parameters Using Various Computer Codes," in Proceedings of the The 35th Annual Canadian Nuclear Society Conference, pp.
Zhang, "Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario," Annals of Nuclear Energy, vol.
Marleau, "Neutronics/Thermalhydraulics coupling in a CANDU SCWR," in Proceedings of the The 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors, CCSC-2012, Xian, China, 2012.
Novog, "Optimization of the canadian scwr core using coupled 3D reactor physics and thermalhyraulics calculations," Journal of Nuclear Engineering and Radiation Science, 2017.
Anghel, "Parameters for transient response modeling for the Canadian SCWR," in Proceedings of the The 19th Pacific Basin Nuclear Conference (PBNC-2014), Vancouver, Canada, 2014.
Zhang, "Safety analysis code SCTRAN development for SCWR and its application to CGNPC SCWR," Annals of Nuclear Energy, vol.