Technical and Methodological Support for Studies of Radioactive Graphite-containing Sludge in Technological Reservoirs

被引：0
|
作者：
A. O. Pavlyuk
S. G. Kotlyarevsky
A. A. Zaderyaka
V. A. Kuzov
O. M. Shevchenko
E. V. Zakharova
A. G. Volkova
机构：
[1] Pilot and Demonstration Center for Decommissioning of Uranium-Graphite Nuclear Reactors,
[2] Frumkin Institute of Physical Chemistry and Electrochemistry,undefined
[3] Russian Academy of Sciences,undefined
来源：
Radiochemistry | 2022年 / 64卷
关键词：
graphite-containing sludge; irradiated graphite; radiation examination; decommissioning; deposits;
D O I：
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学科分类号：
摘要：
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页码：750 / 756
页数：6
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  • [1] Technical and Methodological Support for Studies of Radioactive Graphite-containing Sludge in Technological Reservoirs
    Pavlyuk, A. O.
    Kotlyarevsky, S. G.
    Zaderyaka, A. A.
    Kuzov, V. A.
    Shevchenko, O. M.
    Zakharova, E. V.
    Volkova, A. G.
    RADIOCHEMISTRY, 2022, 64 (06) : 750 - 756
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