Title: Development of technology for high-level radwaste treatment to ceramic matrix by method of self-propagating high-temperature synthesis

Authors: O.A. Yarmolenko, A.A. Romenkov, N.A. Sudareva, E.V. Sukhovski, E.E. Konovalov, N.G. Bogdanovich, O.K. Karlina, G.A. Pvolova, A.Yu. Yurchenko

Addresses: Federal State Unitary Enterprize, N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Russia. ' Federal State Unitary Enterprize, N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Russia. ' Federal State Unitary Enterprize, N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Russia. ' Federal State Unitary Enterprize, N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Russia. ' RF State Research Center – Physics and Power Institute (FEI), Russia. ' RF State Research Center – Physics and Power Institute (FEI), Russia. ' State Unitary Enterprize, Moscow Research and Production Enterprize, Radon, Russia. ' State Unitary Enterprize, Moscow Research and Production Enterprize, Radon, Russia. ' State Unitary Enterprize, Moscow Research and Production Enterprize, Radon, Russia

Abstract: For the purpose of reduction of the risk of spread of transuranic actinides, carbon-14 and other radionuclides contained in the NPP HLW, the Rosenergoatom concern decided to develop a technology of self-propagating high-temperature synthesis (SHS) to obtain a ceramic matrix suitable for long-term and ecologically safe deep geological disposal of the high-level radwaste of the nuclear industry. The proposed graphite HLW treatment method to immobilise the radionuclides into the thermally, chemically and radiation stable carbide-corundum matrix is based on a SHS-process according to the chemical reaction in the system C+Al+TiO₂, where the component C is irradiated graphite of the RBMK reactor core moderators. This paper reports the results of the R&D activities for optimising the SHS technology on a pilot plant using non-irradiated graphite and fuel spill simulators (HLW).

Keywords: radioactive waste treatment; ceramic matrix; self-propagating high-temperature synthesis; irradiated graphite; graphite high level waste; radionuclide immobilisation; radionuclides; carbide corundum matrix; spent nuclear fuel; nuclear reactors; nuclear energy; nuclear power; radiation safety; nuclear safety; nuclear waste disposal; geological disposal; simulation; nuclear science; nuclear technology; Russia.

DOI: 10.1504/IJNEST.2006.010655

International Journal of Nuclear Energy Science and Technology, 2006 Vol.2 No.1/2, pp.144 - 155

Published online: 10 Aug 2006 *

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