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PACKAGE ID001332MLTPL01SAS4A/SASSYS V3.1.2*
KWIC TitleThe SAS4A/SASSYS-1 Safety Analysis Code System 
AUTHORST. H. Fanning, F. E. Dunn, J. E. Cahalan, A. M. Tentner, L. L. Briggs, Kalimullah, J. M. Kramer, K. J. Miles, T. Sofu, R. B. Vilim, R. A. wigeland
LIMITATION/AUDIENCE CODEUNL/UNL
COMPLETION DATE 01/31/2012 
PUBLICATION DATE01/31/2012 
DESCRIPTIONSAS4A/SASSYS-1 is a software simulation tool used to perform deterministic safety analysis of anticipated events as well as design basis and beyond design basis accidents for advanced nuclear reactors. This software can be used to assess the safety of a prescribed reactor design, but it cannot be used to configure a design to meet targeted performance objectives. 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 coolantflow, oss 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 and LBE. METHOD OF SOLUTION: Each subassembly in the reactor core is represented with single or multiple-pin models. One channel represents one or more fuel pins and many channels are employed for a whole-core representation. Heat transfer in each pin is modeled with a two-dimensional (r/z) heat conduction equation. Single and two-phase coolant thermal-hydraulics are simulated with a unique, one-dimensional (axial) multiple-bubble liquid metal boiling model. The transient fuel and cladding mechanical oehavior models are integrated with fission product production,release, and transport models. UNIQUE FEATURES: The physical models in SAS4AJSASSYS-1 are highly detailed 1umerical representations of reactor accident conditions based on extensive laboratory and test reactor results. The models are specialized to liquid metal (sodium) cooled fast reactors with oxide or metallic fuel clad with stainless steel. 
PACKAGE CONTENTSMedia Directory; Software Abstract; Media includes User Guide; Executable Module(s); Sample Problem Input Data; Sample Problem Output Data; / 1 CD-ROM 
SOURCE CODE INCLUDED?
MEDIA QUANTITY
COMPUTERMLT-PLTFM 
OPERATING SYSTEMSGNU/Linux, Mac OS, Microsoft Windows 
SOFTWARE LIMITATIONSExecution time depends on the complexity of the model and the physical phenomena being analyzed 
REFERENCESA 2100 page manual is included with the software: The SAS4A/SASSYS-1 Safety Analysis Code System, ANL/NE-12/4, Argonne National Laboratory, January 31, 2012 Additional Resources: https:wiki.anl.gov/sas/SAS 
ABSTRACT STATUSReleased As-Is 02/15/2012 
SPONSORUSDOE 
RESEARCH ORGArgonne National Laboratory 
PACKAGE TYPEAS-IS 

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