Radioactivity Category Determination for Radiation-Protection Concrete in Nuclear Facilities Undergoing Decommissioning


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Abstract

The classification used during the decommissioning of nuclear installations for the activated materials of radiation protection made of concrete is validated. It is shown that in the decommissioning of nuclear installations the category of activated wastes that are formed, including owing to the large and sometimes determining contribution of 3H in the total induced activity of the concrete with decay times up to 100 years, can be interpreted loosely. The requirements of handling tritium-containing wastes have not been developed.

About the authors

B. K. Bylkin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

A. N. Kozhevnikov

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

I. A. Engovatov

Moscow State University of Civil Engineering (National Research University)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

D. K. Sinyushin

Moscow State University of Civil Engineering (National Research University)

Email: j-atomicenergy@yandex.ru
Russian Federation, Moscow

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