Response of a pool-type LMR (liquid metal reactor) to seismic loads
Conference
·
OSTI ID:5677872
- Argonne National Lab., IL (USA)
This paper describes the seismic analysis of a 450-MWe pool-type liquid metal reactor (LMR) under 0.3 g SSE ground excitations. It also assess the ultimate inelastic structural capabilities for other beyond-design-basis seismic events. Calculation is focused on a new design configuration where the vessel thickness is reduced considerably compared to the previous design (Ma and Gvildys, 1987). In the analysis, the stress and displacement fields at important locations of the reactor vessel, guard vessel, and support skirt are investigated. Emphasis is placed on the horizontal excitation in which large stress is generated. The possibility of impact between the reactor and guard vessels is examined. In the reactor vessel analysis, the effect of fluid-structure interaction is included. Attention is further given to the maximum horizontal acceleration of the reactor core as well as the relative displacement between the reactor core and the upper internal structure. The Argonne National Laboratory augmented three-dimensional Fluid-Structure Interaction program, FLUSTR-ANL is utilized for performing the base calculation where ground excitation is assumed to be 0.3 g SSE. The Newmark-Hall Ductility modification method was used for the beyond-design-basis seismic events. In both calculations, stress fields generated from the horizontal and vertical excitations are evaluated separately. The resultant stresses due to combined actions of these events are computed by the SRSS method. 4 refs., 5 figs., 2 tabs.
- Research Organization:
- Argonne National Lab., IL (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5677872
- Report Number(s):
- CONF-890855-53; ON: DE89017699
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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22 GENERAL STUDIES OF NUCLEAR REACTORS
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99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BREEDER REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
EPITHERMAL REACTORS
F CODES
FAST REACTORS
FBR TYPE REACTORS
FUNCTIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL STRUCTURES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RESONANCE
RESPONSE FUNCTIONS
SAFETY
SEISMIC EFFECTS
SIMULATION
STRESS ANALYSIS
STRUCTURAL MODELS
SUPPORTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
A CODES
BREEDER REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINERS
EPITHERMAL REACTORS
F CODES
FAST REACTORS
FBR TYPE REACTORS
FUNCTIONS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICAL STRUCTURES
REACTOR SAFETY
REACTOR VESSELS
REACTORS
RESONANCE
RESPONSE FUNCTIONS
SAFETY
SEISMIC EFFECTS
SIMULATION
STRESS ANALYSIS
STRUCTURAL MODELS
SUPPORTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS