Structural response of 1/20-scale models of the Clinch River Breeder Reactor to a simulated hypothetical core-disruptive accident
Five experiments were performed to help evaluate the structural integrity of the reactor vessel and head design and to verify code predictions. In the first experiment (SM 1), a detailed model of the head was loaded statically to determine its stiffness. In the remaining four experiments (SM 2 to SM 5), models of the vessel and head were loaded dynamically under a simulated 661 MW-s hypothetical core disruptive accident (HCDA). Models SM 2 to SM 4, each of increasing complexity, systematically showed the effects of upper internals structures, a thermal liner, core support platform, and torospherical bottom on vessel response. Model SM 5, identical to SM 4 but more heavily instrumented, demonstrated experimental reproducibility and provided more comprehensive data. The models consisted of a Ni 200 vessel and core barrel, a head with shielding and simulated component masses, and an upper internals structure (UIS).
- Research Organization:
- SRI International, Menlo Park, CA (United States)
- DOE Contract Number:
- AT03-76SF71023
- OSTI ID:
- 6143606
- Report Number(s):
- DOE/SF/71023-T3; ON: DE81026721
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CLINCH RIVER BREEDER REACTOR
REACTOR CORE DISRUPTION
SIMULATION
REACTOR SAFETY EXPERIMENTS
EXPERIMENTAL DATA
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
COMPUTER CODES
EXPLOSIONS
MOCKUP
R CODES
WATER
ACCIDENTS
BREEDER REACTORS
DATA
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HYDROGEN COMPOUNDS
INFORMATION
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NUMERICAL DATA
OXYGEN COMPOUNDS
POWER REACTORS
REACTOR ACCIDENTS
REACTORS
SODIUM COOLED REACTORS
STRUCTURAL MODELS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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