The development and testprogram of transport and storage casks for vitrified high level wastes
- GNS Gesellschaft, Hannover (Germany)
Reprocessing of irradiated fuel assemblies generates canisters filled with vitrified high level radioactive waste (HLW). The canisters are made of stainless steel and welded leak-tight. These HLW canisters are subject to transport from the fuel reprocessing plant to intermediate and final storage. Since 1983, a number of different packages based on the type B(U) concept of the IAEA were therefore designed, tested, licensed and manufactured for the transport and the interim storage of HLW canisters in flasks. The theoretical layout of the cask was tested by measurements on a prototype cask of the scale 1:1. The measured heat transfer characteristics of this newly developed transport and storage cask will be described. They can be written as a function Nu - C * Ra{sup m}, with the variable factor C, and the constant exponent m., The factor C is different for the vertical and the horizontal position of the cask.
- OSTI ID:
- 103032
- Report Number(s):
- CONF-920430--Vol.2
- Country of Publication:
- United States
- Language:
- English
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