The hydraulic wash and corrosion experiment of CARR U3Si2-Al fuel
Zhang Yingchao; Gao Yongguang; Huang Xin; Kang Yalun; Chen Lixia
Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.4--nuclear material2010
Progress report on nuclear science and technology in China (Vol.1). Proceedings of academic annual meeting of China Nuclear Society in 2009, No.4--nuclear material2010
AbstractAbstract
[en] U3Si2-Al Dispersion Fuel is one of the important fuel used in the research and testing reactors in the world. The objective of the experiment is investigation of the structure stability of the fuel. The experiment is different from the previous experiments in which the samples are tested for 168 hours in the boiling water of 100 degree C. In this experiment the samples are tested for 168 hours under the conditions to simulate CARR operation for which the water velocity is 10 m/s, and fuel temperature is 154 degree C. The samples are divided three groups, the first group without exposed fuel, the second with the smaller area of exposed fuel, and the third with the bigger area of exposed fuel. The Measurement of the uranium content in the water and the sample weight is used to investigate the structure stability of the fuel, and the anti-corrosion performance of the fuel. (authors)
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Chinese Nuclear Society, Beijing (China); 284 p; ISBN 978-7-5022-5040-9; ; Nov 2010; p. 35-39; '09: academic annual meeting of China Nuclear Society; Beijing (China); 18-20 Nov 2009; 6 figs., 2 tabs., 2 refs.
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Conference
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