Carbonate of strontium anchored at the edge of graphite

Author:

Zhang Wei,Zhu Hongwei,Gao Zelin,Wang TaoweiORCID,Wendurina ,Xu Gang,Hu Shu-Xian,Chen XiaotongORCID,Liu Bing,Tang Yaping

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference45 articles.

1. A comprehensive review on decontamination of irradiated graphite waste;Fu;J. Nucl. Mater.,2022

2. Damage tolerance of nuclear graphite at elevated temperatures;Liu;Nat. Commun.,2017

3. Radiochemical characterisation of graphite from Juelich experimental reactor (AVR);Bisplinghoff;International Atomic Energy Agency,2001

4. Electrochemical decontamination of irradiated nuclear graphite from corrosion and fission products using molten salt;Grebennikova;Energy Environ. Sci.,2021

5. The effect of microstructure on air oxidation resistance of nuclear graphite;Contescu;Carbon,2012

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