Structural response of reactor-core hexcan subassemblies subjected to dynamic overpressurization under accident conditions
Description
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
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- ANL/RE/CP--79101
Conference
- Title
- Pressure vessels and piping conference.
- Dates
- 25-29 Jul 1993.
- Place
- Denver, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25003375
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURES; FINITE ELEMENT METHOD; FUEL PINS; LMFBR TYPE REACTORS; MECHANICAL STRUCTURES; PRESSURIZATION; REACTOR ACCIDENTS; REACTOR SAFETY; RESPONSE FUNCTIONS; S CODES; STAINLESS STEEL-316; STRUCTURAL MODELS
- Descriptors DEC
- ACCIDENTS; ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CALCULATION METHODS; CARBON ADDITIONS; COMPUTER CODES; FBR TYPE REACTORS; FUEL ELEMENTS; FUNCTIONS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; NUMERICAL SOLUTION; REACTOR COMPONENTS; REACTORS; SAFETY; STEEL-CR17NI12MO3; STEELS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38
- Notes
- OSTI as DE93015546; NTIS; INIS; US Govt. Printing Office Dep.
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-930702--32.