The Design of Transport Containers for Radioactive Waste Materials
This paper describes the design process related to the development of a family of transport containers for intermediate level radioactive waste materials. These steel containers, each large enough to carry four 500 litre drums full of immobilised waste, all have similar internal cavities, but have wall thicknesses chosen for the activity levels of the waste streams to be transported. Four different wall thicknesses have been chosen, ranging from 70mm at the lightest end of the spectrum to 285mm at the heaviest end.
Three principal steps are described in the paper. First, a series of simple calculations is used to identify concepts which have the potential to satisfy the design aims. Following this, a concept appraisal identifies the preferred scheme and more elaborate computer-aided calculations are used to confirm its adequacy and develop the details of the design. Finally, some scale model prototypes are manufactured and tested to prove their performance under extreme load conditions and to validate the predictive modelling.
The paper outlines some of the methods which have been used for the development of components such as shock-absorbers and fasteners and shows how relatively simple calculations can be used to obtain preliminary sizings. Some attention is also paid to more advanced analytical methods (such as impact prediction using finite element techniques) and examples are also given of the use of computers to produce 3-D visualisation of the concepts in the early stages of a project.
KeywordsShock Absorber Force Diagram Irradiate Fuel Transport Container High Strength Bolt
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- Atom Number 344 June 1985 pp 25-29.Google Scholar
- Dallard, P.R.B., 1985, Flask Analytical Studies in “The Resistance to Impact of Spent Magnox Fuel Transport Flasks”, Mechanical Engineering Publications.Google Scholar
- Donelan, P.J. and Dowling, A.R. 1985, The use of Scale Models in Impact Testing in “The Resistance to Impact of Spent Magnox Fuel Transport Flasks”, Mechanical Engineering Publications.Google Scholar
- Donelan, P., Milloy, C., Miles, J.C., Marlow, B., 1986, The Mechanical Properties of Immobilised Intermediate Level Waste, in “Proceedings of 8th International Symposium on The Packaging and Transportation of Radioactive Materials” (PATRAM 86), Davos, Switzerland.Google Scholar
- International Atomic Energy Agency Safety Series 6, 1985, “Regulations for the Safe Transport of Radioactive Materials”.Google Scholar
- Hallquist, J.O., 1987, “DYNA3D Users Manual”. UCID-19592, Revision 3. Lawrence Livermore National Laboratory, California.Google Scholar
- Nirex Press Release November 1984.Google Scholar
- Smith, M.J.S., and Marlow, B., 1987, The Packaging and Transport of Radioactive Waste in “IMechE Seminar on the Management & Disposal of Intermediate and Low Level Radioactive Waste”, Mechanical Engineering Publications.Google Scholar