Analysis, scale modeling, and full-scale test of a railcar and spent-nuclear-fuel shipping cask in a high-velocity impact against a rigid barrier
This report describes the mathematical analysis, the physical scale modeling, and a full-scale crash test of a railcar spent-nuclear-fuel shipping system. The mathematical analysis utilized a lumped-parameter model to predict the structural response of the railcar and the shipping cask. The physical scale modeling analysis consisted of two crash tests that used 1/8-scale models to assess railcar and shipping cask damage. The full-scale crash test, conducted with retired railcar equipment, was carefully monitored with onboard instrumentation and high-speed photography. Results of the mathematical and scale modeling analyses are compared with the full-scale test. 29 figures.
- Research Organization:
- Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6393764
- Report Number(s):
- SAND-78-0458; TTC-0087; ON: DE81027296; TRN: 81-013290
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
SPENT FUEL CASKS
IMPACT TESTS
ACCIDENTS
DAMAGE
RAIL TRANSPORT
RAILROAD CARS
RESPONSE FUNCTIONS
CASKS
CONTAINERS
FUNCTIONS
LAND TRANSPORT
MATERIALS TESTING
MECHANICAL TESTS
TESTING
TRAINS
TRANSPORT
VEHICLES
420204* - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
SPENT FUEL CASKS
IMPACT TESTS
ACCIDENTS
DAMAGE
RAIL TRANSPORT
RAILROAD CARS
RESPONSE FUNCTIONS
CASKS
CONTAINERS
FUNCTIONS
LAND TRANSPORT
MATERIALS TESTING
MECHANICAL TESTS
TESTING
TRAINS
TRANSPORT
VEHICLES
420204* - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
& Storage