Transient behavior of a scaled RCCS test facility under postulated fault and accident scenarios
Tests were performed on the Natural convection Shutdown heat removal Test Facility (NSTF) to simulate design basis accident and postulated fault scenarios. Residing at Argonne National Laboratory, the NSTF stands nearly 26-m in total height and reflects a ½ scale reactor cavity cooling system (RCCS) for high temperature gas cooled reactors. The following manuscript details three test conditions performed on the experimental test facility. The first simulated the reactor pressure vessel (RPV) boundary condition during depressurized conduction cool down accident with small primary leak, and was repeated during both winter and summer seasons. The second examined a short-circuit break between the inlet and outlet flow paths, and was performed in three incremental stages of nominal flow area break size. The third and final test case studied system behavior with varying amounts of cooling channel blockages, up to and including 50% flow areas. Nominal component temperatures, heat removal performance, and system stability will be presented to characterize the behavior at these conditions.
- Research Organization:
- Argonne National Lab. (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy - Office of Nuclear Reactor Technologies - Advanced Reactor Technologies (ART)
- DOE Contract Number:
- AC02-06CH11357
- OSTI ID:
- 1335906
- Resource Relation:
- Conference: 11th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety, 10/09/16 - 10/13/16, Gyeongju, KR
- Country of Publication:
- United States
- Language:
- English
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