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By M. Shavit

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12. The option also exists to add mass to the pebbles, causing them to sink in the coolant and permitting refueling via a process similar to that for the existing PBRs. 3 STRINGER OR ASSEMBLY HIGH-TEMPERATURE REACTORS The AGRs are graphite-moderated carbon dioxide−cooled high-temperature reactors that use stainlesssteel-clad oxide fuel assemblies. Because of advances in technology, a liquid-salt cooled variant of these reactors appears feasible, provided that the metal components of the fuel assembly are replaced with carbon composite materials.

1 COMMON SODIUM AND SALT REFUELING CHARACTERISTICS Excluding military and space reactors, approximately 20 sodium-cooled fast reactors have been built in a variety of sizes and configurations. These vary from small test reactors to the French Super-Phenix plant, which had an output of 1240 MW(e). In the United States, several fast reactors were built. These included the EBR-II and the Fast-Flux Test Facility (FFTF)─a 400-MW(t) reactor. The Clinch River Breeder Reactor Plant (CRBRP), a commercial demonstration reactor, was designed and partly built before being cancelled.

0 m Fig. 6. Vertical cross-section of the AHTR-MI for normal operation (left) and refueling (right) modes. IHX = intermediate heat exchanger; DHX = decay heat exchanger; PHX = pool heat exchanger. ) This option has the potential to significantly reduce refueling time by avoiding SNF cask operations that include (1) transferring SNF to a cask, (2) closing the cask, (3) decoupling the cask from the reactor lid, (4) moving the cask to the SNF storage area, (5) coupling the cask to the SNF storage area, (6) opening the cask, (7) transferring the SNF to the storage area, and (8) each of these operations in reverse for the fresh fuel.

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