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Title: The role of SASSYS-1 in LMR (Liquid Metal Reactor) safety analysis

The SASSYS-1 liquid metal reactor systems analysis computer code is currently being used as the principal tool for analysis of reactor plant transients in LMR development projects. These include the IFR and EBR-II Projects at Argonne National Laboratory, the FFTF project at Westinghouse-Hanford, the PRISM project at General Electric, the SAFR project at Rockwell International, and the LSPB project at EPRI. The SASSYS-1 code features a multiple-channel thermal-hydraulics core representation coupled with a point kinetics neutronics model with reactivity feedback, all combined with detailed one-dimensional thermal-hydraulic models of the primary and intermediate heat transport systems, including pipes, pumps, plena, valves, heat exchangers and steam generators. In addition, SASSYS-1 contains detailed models for active and passive shutdown and emergency heat rejection systems and a generalized plant control system model. With these models, SASSYS-1 provides the capability to analyze a wide range of transients, including normal operational transients, shutdown heat removal transients, and anticipated transients without scram events. 26 refs., 16 figs.
Authors:
;
Publication Date:
OSTI Identifier:
7010985
Report Number(s):
CONF-880506-4
ON: DE88009939
DOE Contract Number:
W-31109-ENG-38
Resource Type:
Conference
Resource Relation:
Conference: Safety of next generation power reactors, Seattle, WA, USA, 1 May 1988
Research Org:
Argonne National Lab., IL (USA)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; LIQUID METAL COOLED REACTORS; REACTOR SAFETY; REACTOR SHUTDOWN; COMPUTER CODES; REACTOR CORES; S CODES; TRANSIENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SHUTDOWNS 220400* -- Nuclear Reactor Technology-- Control Systems