Impact analysis of shipping casks
Shipping casks are being used in the United States Department of Energy to transport irradiated experiments, reactor fuel, radioactive waste, etc. One of the critical requirements in shipping cask analysis is the necessity to withstand severe impact environments. It is still conventional to develop the design and to verify the design requirements by hand calculations. Full three dimensional computations of impact scenarios have been performed but they are too expensive and time consuming for design purposes. Typically, on the order of more than an hour of CRAY time is required for a detailed, three dimensional analysis. The paper describes how simpler two- and three-dimensional models can be used to provide an intermediate level of detail between full three dimensional finite element calculations and hand calculations. The regulation that is examined here is: 10 CFR-71.73 hypothetical accident conditions, free drop. Free drop for an accident condition of a Class I package (approximate weight of 22,000 lb) is defined as a 30 foot drop onto a flat, essentially unyielding, horizontal surface, striking the surface in a position for which maximum damage is expected. Three free drop scenarios are analyzed to assess the integrity of the cask when subjected to large bending and axial stresses. These three drop scenarios are: (1) a thirty foot axial drop on either end, (2) a thirty foot oblique angle drop with the cask having several different orientations from the vertical with impact on the top end cask corner, and (3) a thirty foot side drop with simultaneous impact on the strength of the various components that comprise the cask. The predicted levels of deformation and stresses in the cask will be used to assess the potential damage level. 5 refs., 5 figs., 1 tab.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5947223
- Report Number(s):
- CONF-890855-35; ON: DE89012423
- Resource Relation:
- Conference: 10. international conference on Structural Mechanics in Reactor Technology (SMIRT), Anaheim, CA, USA, 14-18 Aug 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
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IMPACT STRENGTH
ACCIDENTS
FINITE ELEMENT METHOD
RADIOACTIVE MATERIALS
REGULATIONS
SIMULATION
SPENT FUEL CASKS
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MATERIALS
MECHANICAL PROPERTIES
NUMERICAL SOLUTION
420204* - Engineering- Shipping Containers
050900 - Nuclear Fuels- Transport
Handling
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