Validation of detailed thermal hydraulic models used for LMR safety and for improvement of technical specifications

Conference · Sun Dec 31 00:00:00 EST 1995

OSTI ID:198687

Dunn, F E

Detailed steady-state and transient coolant temperatures and flow rates from an operating reactor have been used to validate the multiple pin model in the SASSYS-1 liquid metal reactor systems analysis code. This multiple pin capability can be used for explicit calculations of axial and lateral temperature distributions within individual subassemblies. Thermocouples at a number of axial locations and in a number of different coolant sub-channels m the XXO9 instrumented subassembly in the EBR-II reactor provided temperature data from the Shutdown Heat Removal Test (SHRT) series. Flow meter data for XXO9 and for the overall system are also available from these tests. Results of consistent SASSYS-1 multiple pin analyses for both the SHRT-45 loss-of-flow-without-scram-test and the S14RT-17 protected loss-of-flow test agree well with the experimental data, providing validation of the SASSYS-1 code over a wide range of conditions.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 198687
• Report Number(s): ANL/RA/CP-85314; CONF-950914-9; ON: DE96004804
• Resource Relation: Conference: American Nuclear Society international topical conference on the safety of operating reactors, Seattle, WA (United States), 17-23 Sep 1995; Other Information: PBD: [1995]
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
22 NUCLEAR REACTOR TECHNOLOGY
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
LMFBR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
REACTOR CHANNELS
S CODES
VALIDATION
TEMPERATURE DISTRIBUTION
REACTOR SAFETY
FLOW RATE
REACTOR COOLING SYSTEMS