Thus far only thermal-hydraulic driven accident scenarios (LOCA, LOFA) have been investigated for the Canadian SCWR. While the coolant void reactivity (CVR) for the design was negative, studies demonstrate a positive reactivity insertion under nonequilibrium voiding conditions [13, 14].
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.
The data shown in this study indicate that partially dissolution of a Mo-bearing passivation layer in a SCWR may affect water chemistry and the efficiency of the reactor.
Guzonas, "Corrosion database for SCWR development," in Proceedings of the 2nd Canada-China Joint Workshop on Supercritical-Water-Cooled Reactors, 2010.
Baindur, "Materials challenges for the supercritical water-cooled reactor (SCWR)," Bulletin of the Canadian Nuclear Society, vol.
SCTRAN is originally a transient analysis code for supercritical water reactor (SCWR).
Zhang, "Safety analysis code SCTRAN development for SCWR and its application to CGNPC SCWR," Annals of Nuclear Energy, vol.
SCTRAN is a one-dimensional safety analysis code for SCWRs, which applies homogeneous model to simulate the fluid flow.