Structural response of reactor-core hexcan subassemblies subjected to dynamic overpressurization under accident conditions

Conference · Tue Jun 01 00:00:00 EDT 1993

OSTI ID:10166509

Pfeiffer, P A; Kulak, R F

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, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 10166509
• Report Number(s): ANL/RE/CP-79101; CONF-930702-32; ON: DE93015546; TRN: 93:016420
• Resource Relation: Conference: 1993 American Society of Mechanical Engineers (ASME) pressure vessel and piping conference,Denver, CO (United States),25-29 Jul 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
FUEL PINS
FAILURES
RESPONSE FUNCTIONS
PRESSURIZATION
STRUCTURAL MODELS
MECHANICAL STRUCTURES
REACTOR SAFETY
REACTOR ACCIDENTS
S CODES
FINITE ELEMENT METHOD
STAINLESS STEEL-316
220900
210500
POWER REACTORS
BREEDING