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SUMMARYThe objective of the research described in this report was to conduct a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and subsequent transportation. The use of fill material to stabilize used nuclear fuel is not considered to be a primary option for safely transporting used nuclear fuel after extended storage. However, the evaluation of potential fill materials, such as those described in this report, might provide the U.S. Department of Energy Used Fuel Disposition Campaign with an option that would allow continued safe storage and transportation if other options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.As a first step in evaluating fill materials, previous work done in this area was summarized. This involved studies done by the Spent Fuel Stabilizer Materials Program, Allied-General Nuclear Services, the Canadian Nuclear Fuel Waste Management Program, the U.S. Department of Energy, Spain, Sweden, and the Department of Energy's Yucca Mountain Project. A wide variety of potential fill materials were evaluated in these studies, ranging from molten metal to particulates and beads to liquids and gases. The common element in the studies was that they were focused on the use of fill materials in waste packages for disposal, not in storage canisters or transportation casks. In addition, very few studies involved actual experiments that measured some physical property of the fill material to be used as a stabilizing material, and no studies were found that analyzed the performance of transportation casks containing fill material during the normal conditions of transport specified in 10 CFR 71.71 or under hypothetical accident conditions specified in 10 CFR 71.73. In addition, most studies did not address issues that would be associated with production-scale emplacement of fill material in canisters, as opposed to laboratory-or experimental-scale use of fill material. It is noteworthy that Sweden abandoned its plan to use fill materials to stabilize waste packages due to the complexity of emplacing the fill material.As part of the evaluation of fill materials, conceptual descriptions of how canisters might be filled were developed with different concepts for liquids, particles, and foams. The requirements for fill materials were also developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations.Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; partic...
SUMMARYThe objective of the research described in this report was to conduct a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and subsequent transportation. The use of fill material to stabilize used nuclear fuel is not considered to be a primary option for safely transporting used nuclear fuel after extended storage. However, the evaluation of potential fill materials, such as those described in this report, might provide the U.S. Department of Energy Used Fuel Disposition Campaign with an option that would allow continued safe storage and transportation if other options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.As a first step in evaluating fill materials, previous work done in this area was summarized. This involved studies done by the Spent Fuel Stabilizer Materials Program, Allied-General Nuclear Services, the Canadian Nuclear Fuel Waste Management Program, the U.S. Department of Energy, Spain, Sweden, and the Department of Energy's Yucca Mountain Project. A wide variety of potential fill materials were evaluated in these studies, ranging from molten metal to particulates and beads to liquids and gases. The common element in the studies was that they were focused on the use of fill materials in waste packages for disposal, not in storage canisters or transportation casks. In addition, very few studies involved actual experiments that measured some physical property of the fill material to be used as a stabilizing material, and no studies were found that analyzed the performance of transportation casks containing fill material during the normal conditions of transport specified in 10 CFR 71.71 or under hypothetical accident conditions specified in 10 CFR 71.73. In addition, most studies did not address issues that would be associated with production-scale emplacement of fill material in canisters, as opposed to laboratory-or experimental-scale use of fill material. It is noteworthy that Sweden abandoned its plan to use fill materials to stabilize waste packages due to the complexity of emplacing the fill material.As part of the evaluation of fill materials, conceptual descriptions of how canisters might be filled were developed with different concepts for liquids, particles, and foams. The requirements for fill materials were also developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations.Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; partic...
The results from 80-week boil-down tests are located in Table 4-6. Section 6.2.1.3 provides further explanation on the use of these rates. 4.1.3.1.4 Radiolysis The results of experiments simulating the effects of radiolysis products on corrosion can be found in Table 4-7. Section 6.2.1.4 further explains the use of these rates. 4.1.3.1.5 Sensitization of Stainless Steel This section does not report any data on corrosion of sensitized stainless steel. The rationale for this can be found in Section 6.2.1.5. 4.1.3.2 Steels Containing Neutron Absorbers (Boron and Gadolinium)
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