16 research outputs found
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Test plan for surface and subsurface examinations of K-east and K-west fuel elements
The test plan for subsurface examinations on damaged K East and K West Basin fuel elements is presented. The purpose of these examinations is to inspect damaged areas on the fuel elements for the presence of voids, sludge, or broken fuel, and to obtain samples from the damaged areas for subsequent characterization tests
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Initial assessment of K west fuel condition based on K eastcleanliness evaluation categories
Recent in-basin examinations of K West fuel were conducted and the defect frequencies were assessed in terms of `minor` and `major` damage. To be consistent with previous damage assessments of K East fuel, the defect categorizations were converted to similar classifications. For the outer elements examined in the K West campaign, 50% are Intact, 26% are Breached, 0% are Defected, and 24% are in the Bad category
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IN-CELL visual examinations of K east fuel elements
Nine outer fuel elements were recovered from the K East Basin and transferred to a hot cell for examination. Extensive testing planned for these elements will support the process design for the Integrated Process Strategy (IPS), with emphasis on drying and conditioning behavior. Visual examinations of the fuel elements confirmed that they are appropriate to meet testing objectives to provide design guidance for IPS processing parameters
WDC-1-1 instrumented irradiation of boron carbide in a spectrum-hardened ETR flux
Boron carbide pellets were irradiated in a spectrum-hardened ETR flux at temperatures of 1220 to 1620 deg F up to maximum specimen-averaged exposures of 38 x 10/sup 20/ captures/cm/sup 3/. Material variables included pellet density (75 to 99% T. D.) and stoichiometry (B: C = 3.8 to 4.1). Gas release and irradiation temperature were continuously monitored during the irradiation. Results are reported for boron carbide structural degradation, helium release, and interaction with Type 316 stainless steel. (auth
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KE Basin underwater visual fuel survey
Results of an underwater video fuel survey in KE Basin using a high resolution camera system are presented. Quantitative and qualitative information on fuel degradation are given, and estimates of the total fraction of ruptured fuel elements are provided. Representative photographic illustrations showing the range of fuel conditions observed in the survey are included
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Liquid metal reactor absorber technology
The selection of boron carbide as the reference liquid metal reactor absorber material is supported by results presented for irradiation performance, reactivity worth compatibility, and benign failure consequences. Scram response requirements are met easily with current control rod configurations. The trend in absorber design development is toward larger sized pins with fewer pins per bundle, providing economic savings and improved hydraulic characteristics. Very long-life absorber designs appear to be attainable with the application of vented pin and sodium-bonded concepts. 3 refs., 3 figs
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HIGH-TEMPERATURE IRRADIATIONS (1000 TO 1300C) ON A VARIETY OF GRAPHITES TO EXPOSURES > 10 n/cm .
K East canister sludge survey
Sludge depths were measured in 60 selected canisters in the K East Basin. The projected K East basin total canister sludge inventory based on these measurements is 3 cubic meters. After sludge samples were extracted from 12 canisters, the sludge depth measurements were repeated to confirm adequate sample volumes had been obtained to perform prescribed analytical and testing activities
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K East canister sludge survey
Sludge depths were measured in 60 selected canisters in the K East Basin. The projected K East basin total canister sludge inventory based on these measurements is 3 cubic meters. After sludge samples were extracted from 12 canisters, the sludge depth measurements were repeated to confirm adequate sample volumes had been obtained to perform prescribed analytical and testing activities