Mass spectrometric studies on irradiated (U, Pu) mixed carbide fuel of FBTR
by R. Balasubramanian,, D. Darwin Albert Raj, S. Nalini, M. Sai Baba
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 1, No. 2/3, 2005

Abstract: 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.

Online publication date: Sun, 29-May-2005

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