Immobilization of carbon-14 from reactor graphite waste by use of self-sustaining reaction in the C–Al

Immobilization of carbon-14 from reactor graphite waste by use of self-sustaining reaction in the C–Al–TiO2 system

Published:2005-10 Issue:1 Volume:345 Page:84-85
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Karlina O.K.,Klimov V.L.,Ojovan M.I.,Pavlova G.Yu.,Dmitriev S.A.,Yurchenko A.Yu.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. Radiation characteristics of graphite removed from operation in uranium-graphite reactors

2. A.G. Merzhanov, I.P. Borovinskaya, N.S. Makhonin, V.V. Zakorzhevsky, E.E. Konovalov, F.D. Lisitsa, O.V. Starkov, M.P. Myshkovsky, Patent RU 2065220, priority 18 March 1994.

3. V.L. Klimov, O.K. Karlina, G.Yu. Pavlova, M.I. Ojovan, S.A. Dmitriev, I.A. Sobolev, Patent RU 2192057, priority 28 June 2001.

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