Verification and implications of the multiple pin treatment in the SASSYS-1 LMR systems analysis code

Conference · Tue Mar 01 00:00:00 EST 1994

OSTI ID:10129984

Dunn, F E

As part of a program to obtain realistic, as opposed to excessively conservative, analysis of reactor transients, a multiple pin treatment for the analysis of intra-subassembly thermal hydraulics has been included in the SASSYS-1 liquid metal reactor systems analysis code. This new treatment has made possible a whole new level of verification for the code. The code can now predict the steady-state and transient responses of individual thermocouples within instrumented subassemlies in a reactor, rather than just predicting average temperatures for a subassembly. Very good agreement has been achieved between code predictions and the experimental measurements of steady-state and transient temperatures and flow rates in the Shutdown Heat Removal Tests in the EBR-II Reactor. Detailed multiple pin calculations for blanket subassemblies in the EBR-II reactor demonstrate that the actual steady-state and transient peak temperatures in these subassemblies are significantly lower than those that would be calculated by simpler models.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10129984
• Report Number(s): ANL/RA/CP-79897; CONF-940402-19; ON: DE94007630; TRN: 94:007387
• Resource Relation: Conference: International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994; Other Information: PBD: [1994]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
LMFBR TYPE REACTORS
SYSTEMS ANALYSIS
HEAT TRANSFER
S CODES
HYDRAULICS
EBR-2 REACTOR
REACTOR KINETICS
FUEL PINS
TEMPERATURE MEASUREMENT
PRIMARY COOLANT CIRCUITS
TRANSIENTS
REACTOR SAFETY
220900
210500
990200
POWER REACTORS
BREEDING
MATHEMATICS AND COMPUTERS