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60439. For information about Argonne and its pioneering science and technology programs, see www.anl.gov.

This analysis involves the examination of radionuclide release from metal fuel under conditions that would be typical of design basis and beyond design basis accidents for metal fuel, pool-type SFRs. This includes pin breach under normal operation due to defects, cladding failure at elevated temperatures due to eutectic penetration, and fuel melting conditions due to loss of heat sink/loss of flow scenarios or transient overpowers. Fuel conditions for accident scenarios that typically fall in the residual risk category or beyond for metal fuel, pool-type SFRs, such as core energetics, hypothetical core disruption accidents, or loss of sodium accidents, are not examined, as these accidents may involve very high fuel temperatures, and the possibility of fuel vaporization.Radionuclide release from metal fuel to the primary sodium is examined for fuel conditions typical of design basis and beyond design basis accidents at metal fuel, pool-type SFRs.

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