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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Leona Marshall Libby, M. G. Wurtele, Chris G. Whipple
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 85-98
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A33055
Articles are hosted by Taylor and Francis Online.
It is technically feasible to site a retrievable but permanent surface storage facility for vitrified radioactive wastes in the northwestern Egyptian desert. Present-day commercial vitrification plants are in England and France and produce glass cylinders in the shape of an annulus, ∼9 ft high, clad in a stainless steel can, containing ∼25% of fission product and actinide oxides, weighing ∼10 tonnes, having a volume of ∼70 ft3, releasing ∼1.8 × 101 Btu heat/h. The high-level waste (HLW) glass cylinders, in lead shipping casks, are to be shipped to European ports by truck, sent to Mersa Matruh on the Egyptian coast, about ten at a time in small barges, then offloaded and sent by train a short distance inland to the site. The storage facility envisaged at the site is a concrete-walled round house with a radial crane, equipped with recanning facilities in case of breakage of stainless steel canisters, with a shop for repair of the train as needed, and with a turntable for the engine. Cooling is provided by natural air draft resulting from the canister surface temperature of ∼100°C. If needed, backup cooling is provided by equipment for forced-air drafts and by tanks of water. The canister arrangement is that produced by coaxial vertical stacking; horizontal coaxial arrangements are yet to be analyzed. The site chosen is exposed hard rock close to the Mediterranean in the northwest corner of the Egyptian desert. Groundwater is found at ∼100 m. The rainfall is ∼4 in./yr so that flash floods sometimes occur and surface drains are needed. Winds are mild and temperate. There is no recent seismicity and, judging from the horizontally bedded rock strata, has been none since the cretaceous period. There is no agriculture on the hard rock, no animal grazing, no archaeological ruins, and no present-day human occupation. There are very few indigenous plants, only those able to grow in rock cracks, and a few small animals and birds. Plume studies of the hot cooling air show no perceptible temperature rise beyond the boundaries of the reservation. Radon content of the plume, resulting from a worst-case break and devitrification of a glass cylinder, is not as large as the natural radon content of the desert air beyond the boundaries. Matters that should be more fully examined include alternative methods of solidification of HLW (such as in ceramics), more data on hydrology and meteorology, and a more detailed design of the stacking and cooling systems. Political Egyptian and international acceptability may be studied and may prove to be the most important factor in siting the proposed facility. We conclude that the northwestern Egyptian desert offers a highly promising site for international permanent and retrievable storage of the world’s vitrified radioactive waste for the necessary 500 yr. These findings are based on technical and economic considerations; institutional and political criteria were not part of this study. In a second study, four more deserts of the world were compared for suitable sites. These five deserts will be compared in a subsequent publication.