Development of a phenomenological constitutive model for polyurethane foams
Rigid, closed-cell, polyurethane foam is used in impact limiters in nuclear waste transport containers. During a hypothetical nuclear waste transport accident, the foam is expected to absorb a significant amount of impact energy by undergoing large inelastic volume reductions. Consequently, the crushing of polyurethane foams must be well characterized and accurately modeled to properly analyze a transport container accident. At the request of Sandia National Laboratories, a series of uniaxial, hydrostatic and triaxial compression tests on polyurethane foams were performed by the New Mexico Engineering Research Institute (NMERI). The combination of hydrostatic and triaxial tests was chosen to provide sufficient data to characterize both the volumetric and deviatoric behaviors of the foams and the coupling between the two responses. Typical results from the NMERI tests are included in this paper. A complete description of these tests can be found in Neilsen et al., 1987. Constitutive models that have been used in the past to model foam did not capture some important foam behaviors observed in the NMERI tests. Therefore, a new constitutive model for rigid, closed-cell, polyurethane foams was developed and implemented in two finite element codes. Development of the new model is discussed in this paper. Also, results from analyses with the new model and other constitutive models are presented to demonstrate differences between the various models. 4 refs., 6 figs., 1 tab.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6106300
- Report Number(s):
- SAND-89-0941C; CONF-890631-40; ON: DE89013526
- Country of Publication:
- United States
- Language:
- English
Similar Records
A constitutive theory for rigid polyurethane foam
Unified Creep Plasticity Damage (UCPD) Model for Rigid Polyurethane Foams
Related Subjects
053000 -- Nuclear Fuels-- Environmental Aspects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
420204* -- Engineering-- Shipping Containers
ACCIDENTS
HIGH-LEVEL RADIOACTIVE WASTES
IMPACT TESTS
MATERIALS
MATERIALS TESTING
MATHEMATICAL MODELS
MECHANICAL TESTS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PLASTICS
POLYAMIDES
POLYMERS
POLYURETHANES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SYNTHETIC MATERIALS
TESTING
TRANSPORT
VALIDATION
WASTES