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- W2510181248 abstract "The Canadian supercritical water-cooled reactor (SCWR) is Canada’s contribution to the Generation-IV (GEN-IV) International Forum’s research and development effort toward the study and eventual deployment of advanced nuclear energy systems. All GEN-IV concepts including the SCWR target enhanced safety, improved economics, improved sustainability, and enhanced security relative to present day nuclear reactors. A loss of coolant accident in the SCWR will shut down the reactor due to a large decrease in reactivity. This highly negative coolant void reactivity (CVR) is a contributor to the enhanced safety of the reactor, but it can complicate reactor control. The use of a solid moderator, namely zirconium hydride, as a means of coolant void reactivity adjustment is assessed here. Results suggest that a solid moderator is a viable option for CVR adjustment, provided materials obstacles can be overcome." @default.
- W2510181248 created "2016-09-16" @default.
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- W2510181248 date "2016-07-26" @default.
- W2510181248 modified "2023-09-26" @default.
- W2510181248 title "A SOLID MODERATOR PHYSICS ASSESSMENT FOR THE CANADIAN SCWR" @default.
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- W2510181248 doi "https://doi.org/10.12943/cnr.2016.00009" @default.
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