Analytical and scale modeling techniques for predicting the response of spent-nuclear-fuel shipping systems involved in severe transportation accidents
Conference
·
OSTI ID:6748733
This paper describes techniques which can be utilized to predict the response of a spent-nuclear-fuel transportation system in a severe transportation accident involving a high velocity impact into a rigid barrier or a collision with another vehicle. The techniques reviewed include both mathematical analyses and physical (scale) modeling. The mathematical (computer) modeling can be accomplished in two steps. The first models the overall system including the vehicle and the cask with a lumped-parameter model, which predicts the rigid body motion of the cask as the vehicle crushes. The second step utilizes a detailed dynamic finite element computer model of the cask to calculate deformations which the cask sustains when it encounters a rigid target at a high velocity. The second part of the paper discusses scale models of casks and vehicle systems used to analyze two hypothetical accident situations. The results of the scale model tests and the mathematical analyses are then related to the results of full-scale tests conducted as the last step in the research program. It is shown that the techniques described in the paper can give excellent indications of the response of shipping casks and transport systems involved in severe impact situations. 7 figures.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6748733
- Report Number(s):
- SAND-78-0767C; CONF-780506-14
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
ACCIDENTS
CASKS
CONTAINERS
FUEL ELEMENTS
FUNCTIONS
MATHEMATICAL MODELS
MOCKUP
REACTOR COMPONENTS
RESPONSE FUNCTIONS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
STRUCTURAL MODELS
TRANSPORT
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
ACCIDENTS
CASKS
CONTAINERS
FUEL ELEMENTS
FUNCTIONS
MATHEMATICAL MODELS
MOCKUP
REACTOR COMPONENTS
RESPONSE FUNCTIONS
SPENT FUEL CASKS
SPENT FUEL ELEMENTS
STRUCTURAL MODELS
TRANSPORT