Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
5475204 | Annals of Nuclear Energy | 2017 | 11 Pages |
Abstract
Core design characteristics, fuel cycle performance, and safety analysis of the FHR DR preconcept have been evaluated. The FHR DR core design features a negative or negligible void coefficient throughout a reactor operating cycle. Both single-batch (cartridge) and multiple-batch fuel cycles can be demonstrated in the FHR DR. The single-batch cycle length of the FHR DR core is estimated at between 12 and 18Â months, assuming the successful qualification of composite carbon (C/C) or silicon carbide (SiC/SiC) structural fuel block tie rod material. Fuel cycle performance of the FHR DR is similar to a high temperature gas-cooled reactor. Preliminary safety analysis of the FHR DR indicates that the reactor could be used to demonstrate the inherent safety characteristics of FHR designs.
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Authors
Nicholas R. Brown, Benjamin R. Betzler, Juan J. Carbajo, Aaron J. Wysocki, M. Scott Greenwood, Cole Gentry, A. Louis Qualls,