Incineration – Variant of Handling Irradiated Reactor Graphite

Author:

Kashcheev V. A.,Poluektov P. P.,Ustinov O. A.,Rublevsky V. P.,Shinkarev S. M.,Yatsenco V. N.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. A. A. Romenko, “Results attained: Handling radioactive graphite during decommissioning of uranium-graphite reactors using the technology for oxidation of graphite in salt melts,” Byull. Rosenergoatoma, No. 3, 32–35 (2011).

2. T. B. Aleeva, Experimental Study of the Contamination of the Graphite Masonry of Commercial Reactors by Fission Products and Actinides: Auth. Abstr. Cand. Dissert. Phys.-Math. Sci., MIFI, Moscow (2003).

3. E. V. Borovkov, A. V. Kryuchkov, and V. I. Mikhan, “Main stages of the technological process of dissembling the graphite masonry of the AMB reactor,” in: Problems of Decommissioning of Power Units in the First Phase of the Beloyarskaya NPP, UrO RAN, Ekaterinburg (1994), pp. 22–29.

4. V. D. Bagaev, I. I. Baranov, Yu. I. Kabanov, et al., “Decommissioning of commercial reactors at the Siberian Chemical Combine,” At. Énerg., 80, No. 2, 71–73 (1996).

5. V. I. Bulanenko, V. V. Frolov, and A. G. Nikolaev, “Radiation characteristics of the graphite in decommissioned uranium-graphite reactors,” At. Énerg., 81, No. 4, 304–306.

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