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SAS4A/SASSYS‑1
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SAS4A/SASSYS‑1 is a software simulation tool used to perform
deterministic analysis of anticipated events as well as design basis and
beyond design basis accidents for advanced nuclear reactors.

Detailed, mechanistic models of steady-state and transient thermal,
hydraulic, kinetic, and mechanical phenomena are employed to describe
the response of the reactor core, the reactor primary and secondary
coolant loops, the reactor control and protection systems, and the
balance-of-plant to accidents caused by changes in coolant flow, loss of
heat rejection, or reactivity insertion. The consequences of single and
double-fault accidents can be modeled, including fuel and coolant
heating, fuel and cladding mechanical behavior, core reactivity
feedbacks, coolant loop performance including natural circulation, and
decay heat removal. Analyses are typically terminated upon demonstration
of reactor and plant shutdown to permanently coolable conditions, or
upon violation of design basis margins. The objective of the analysis is
to quantify accident consequences as measured by the transient behavior
of system performance parameters, such as fuel and cladding
temperatures, reactivity, and cladding strain. Originally developed for
analysis of sodium cooled reactors with oxide fuel clad by stainless
steel, the models in SAS4A/SASSYS‑1 were subsequently extended and
specialized to metallic fuel clad with advanced alloys and to several
other coolant options, including lead, LBE, and water.

For information on the most recent version of SAS4A/SASSYS-1, please contact sas@anl.gov.

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	about
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