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The QUENCH-15 experiment investigated the effect of ZIRLO™ cladding material on bundle oxidation and core reflood from maximum bundle temperature of 2150 K. The molten cladding metal at the hottest elevation was localized between outer and inner oxide layers. The analyses of the QUENCH-15 test data indicate a similar global bundle behavior as of bundle experiments QUENCH-14 (M5® claddings) and QUENCH-06 (Zircaloy-4 claddings).
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Spent reactor fuels --- Spent reactor fuels --- Spent reactor fuels --- Storage. --- Management. --- Transportation.
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Spent reactor fuels --- Radioactive substances --- Storage --- Licenses
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Spent reactor fuels --- Storage --- Management. --- U.S. Nuclear Regulatory Commission --- Auditing. --- Rules and practice.
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Radioactive waste disposal --- Spent reactor fuels --- Nuclear power plants --- Government policy. --- Government policy --- Waste disposal. --- Government policy --- Waste disposal.
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Spent reactor fuels --- Storage --- Management. --- U.S. Nuclear Regulatory Commission --- U.S. Nuclear Regulatory Commission --- Auditing. --- Rules and practice.
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Geological repositories. --- Radioactive waste disposal in the ground --- Spent reactor fuels --- Radioactive waste disposal --- Nuclear facilities --- Radioactivity --- Safety measures.
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