Containment of explosions in spherical vessels

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:6899325

Duffey, T A; Greene, J M ^[1]; Baker, W E ^[2]; Lewis, B B ^[3]

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1. Los Alamos National Lab., NM (United States)
2. New Mexico Univ., Albuquerque, NM (United States). Dept. of Mechanical Engineering
3. APTEK, Inc., Colorado Springs, CO (United States)

A correlation of the experimentally recorded dynamic response of a spherical containment vessel with theoretical finite element calculations is presented. Three experiments were performed on the 6-ft-diameter steel vessel using centrally located 12-lb. and 40-lb. high explosive charges. Pressure-time loading on the inner wall of the vessel was recorded for each test using pressure transducers. Resulting dynamic response of the vessel was recorded for each test using strain gages mounted at selected locations on the outer surface of the vessel. Response of the vessel was primarily elastic. A finite element model of the vessel was run using DYNA3D, a dynamic structural analysis code. Pressure loading for the finite element model was based on results from a one-dimensional reactive hydrodynamics code. Correlations between experiments and analysis were generally good for the tests for frequency and strain magnitude at most locations. Comparisons of experimental and calculated pressure-time histories were less satisfactory.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6899325
• Report Number(s): LA-UR-92-4061; CONF-930702-2; ON: DE93005445
• Resource Relation: Conference: Pressure vessel and piping conference, Denver, CO (United States), 25-29 Jul 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
EXPLOSIONS
CONTAINMENT
NUCLEAR POWER PLANTS
CONTAINMENT SHELLS
D CODES
DUCTILITY
FINITE ELEMENT METHOD
MECHANICAL PROPERTIES
PRESSURE EFFECTS
SPHERICAL CONFIGURATION
STRAIN GAGES
TESTING
CALCULATION METHODS
COMPUTER CODES
CONFIGURATION
MEASURING INSTRUMENTS
NUCLEAR FACILITIES
NUMERICAL SOLUTION
POWER PLANTS
TENSILE PROPERTIES
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220200 - Nuclear Reactor Technology- Components & Accessories