Structural response of reactor-core hexcan subassemblies subjected to dynamic overpressurization under accident conditions
This paper presents a two-dimensional structural analysis for the evaluation of a single core subassembly due to internal overpressure associated with possible failure of fuel pins having high fission gas plenum pressure. Structural models are developed for the subassemblies and their surroundings with emphasis on the critical physical aspects of the problem. With these models the strains, deformations and the extent of permanent damage (plastic strain) to the subassemblies can be assessed. The nonlinear structural analyses was performed with a finite element program called STRAW (Structural Transient Response of Assembly Wrappers). This finite element program is applicable to nonlinear large displacement problems. The results of this study indicate that the permanent deformation (damage) is strongly influenced by the rise time (time to reach peak pressure) of the pressure pulse and the pressure in the fuel pin. The rise time is influenced by the opening time of the flow path for release of gas from the fuel pin plenum. Several examples are illustrated with various rise times and pressure magnitudes and the resulting permanent deformation of the hexcan wall.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6152846
- Report Number(s):
- ANL/RE/CP-79101; CONF-930702-32; ON: DE93015546
- Resource Relation:
- Conference: Pressure vessels and piping conference, Denver, CO (United States), 25-29 Jul 1993
- Country of Publication:
- United States
- Language:
- English
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Dynamic structural response of reactor-core subassemblies (hexcans) due to accident overpressurization
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
FAILURES
LMFBR TYPE REACTORS
FINITE ELEMENT METHOD
MECHANICAL STRUCTURES
PRESSURIZATION
REACTOR ACCIDENTS
REACTOR SAFETY
RESPONSE FUNCTIONS
S CODES
STAINLESS STEEL-316
STRUCTURAL MODELS
ACCIDENTS
ALLOYS
AUSTENITIC STEELS
BREEDER REACTORS
CALCULATION METHODS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
COMPUTER CODES
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
FUNCTIONS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MOLYBDENUM ALLOYS
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STEEL-CR17NI12MO3
STEELS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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