Inderscience Publishers

Mass spectrometric studies on irradiated (U, Pu) mixed carbide fuel of FBTR

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Mass spectrometry was employed to characterise the irradiated mixed carbide fuel of fast breeder test reactor (FBTR) for assessing its performance: thermal ionisation mass spectrometry to determine the isotopic composition, concentrations of U, Pu and Nd in the dissolver solutions and to deduce the burn-up, and a quadrupole mass spectrometric system to obtain the percentage release of fission gases (Kr + Xe). A summary and analysis of the results obtained with the fuel at 25,000 and 50,000 MWd/t in these studies is given in this paper.

Keywords: mass spectrometry, spent fuel, burn-up, isotopic composition, fission gas, fast breeder test reactors, FBYR, nuclear power, nuclear energy, irradiated mixed carbide fuel, nuclear fuel cycle

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