Microscopic analysis of irradiated AGR-1 coated particle fuel compacts
نویسندگان
چکیده
منابع مشابه
Identification of Silver and Palladium in Irradiated TRISO Coated Particles of the AGR-1 Experiment
Evidence of the release of certain metallic fission products through intact tristructural isotropic (TRISO) particles has been seen for decades around the world, as well as in the recent AGR-1 experiment at the Idaho National Laboratory (INL). However, understanding the basic mechanism of transport is still lacking. This understanding is important because the TRISO coating is part of the high t...
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A high temperature guarded-comparative-longitudinal heat flow measurement system has been built to measure the thermal conductivity of a composite nuclear fuel compact. It is a steady-state measurement device designed to operate over a temperature range of 300 K to 1200 K. No existing apparatus is currently available for obtaining the thermal conductivity of the composite fuel in a non-destruct...
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Yttria stabilised zirconia (YSZ) inert matrix fuel (IMF) fabricated at PSI and irradiated 3 years in the Halden Material Test Reactor (HBWR) since 2000, has been examined by Electron Probe Microanalysis (EPMA) and Secondary Ion Mass Spectroscopy (SIMS) after irradiation and compared with data gained for the unirradiated material. The examined pellet cross-section was estimated to have an equiva...
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15 صفحه اولAutomatic Characterization of Cross-sectional Coated Particle Nuclear Fuel using Greedy Coupled Bayesian Snakes
We describe new image analysis developments in support of the U.S. Department of Energy’s (DOE) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. We previously reported a non-iterative, Bayesian approach for locating the boundaries of different particle layers in cross-sectional imagery. That method, however, had to be initialized by manual preprocessing where a user must s...
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ژورنال
عنوان ژورنال: Nuclear Engineering and Design
سال: 2014
ISSN: 0029-5493
DOI: 10.1016/j.nucengdes.2013.11.036