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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2027 ANS Winter Conference and Expo
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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
V, V. Rondinella, R. Nasyrow, D. Papaioannou (EC-JRC), E. Vlassopoulos (EPFL), F. Cappia, O. Dieste-Blanco, T. A. G. Wiss (EC-JRC)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 734-740
The consequences of potential accidents causing spent fuel rod failure may involve fuel particles release and dispersion. This paper presents recent results from spent fuel experimental studies performed at JRCKarlsruhe addressing handling/transportation and longterm storage issues. An impact test using a hammer drop device in hot cell was performed on a spent fuel segment from a UO2 PWR rod with a burnup of ~67 GWd/tHM. The segment was not defueled and was repressurized to 40 bar before the test. Similarly to what observed in previous impact tests, only the fuel volume directly affected by the rod fracturing was released. In addition to the fuel material released during the impact, neither further particles release nor "flow-out" type of behaviour was observed by further tapping on the fractured segments after the test. Preliminary particle size distribution analysis of the fuel particles deposited on a second stage filter of the testing chamber collecting particles with size ?8 ?m indicates a log-normal distribution with main particle size of 2.4 ?m and standard deviation of 1.1 ?m. A few sub-micron particles were detected. The detailed analysis of the results, including finer particle fractions, is still ongoing. The final goal of these investigations is to determine criteria and conditions governing the response of spent fuel rods to impact loads and other thermo-mechanical solicitations corresponding to normal and off-normal conditions that may be experienced by the rod during handling, transportation, storage and after extended storage. In addition to impact and other mechanical loading tests, property measurements as a function of accumulated radiation damage are performed on spent fuel and alpha-doped analogues to determine the long term evolution and the potential effects of ageing processes on the mechanical integrity of the spent fuel rod.