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A comprehensive review on decontamination of irradiated graphite waste

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  • NSTL
  • Elsevier
The complete and safe disposal of large irradiated graphite waste from nuclear reactors has attracted worldwide attention. The core target for the treatment of irradiated graphite is to decontaminate the trace radioactive elements. The reviewed investigation mainly focused on the performance of the decon-tamination method of irradiated graphite based on the current available literature. Survey to fabrication, structure and radioactivity of nuclear graphite was first introduced. Several common treatment technolo-gies (incineration, thermal treatment, electrochemical or chemical treatment, plasma technique, molten salt flameless oxidation and self-sustaining high-temperature synthesis) were summarized. The recom-mendations, standpoints and potential research on the decontamination method of irradiated graphite were highlighted. The work presented would contribute to the information and experience to build de-contamination methods and develop new technologies.(c) 2021 Elsevier B.V. All rights reserved.

Irradiated graphiteDecontaminationRadionuclideTreatment methodNuclear reactorsHIGH-TEMPERATURE SYNTHESISNUCLEAR GRAPHITETHERMAL-TREATMENTMICROSTRUCTURAL CHARACTERIZATIONTHERMODYNAMIC ANALYSISRADIOACTIVE GRAPHITENEUTRON-IRRADIATIONION IRRADIATIONC-14OXIDATION

Fu, Kun、Chen, Meiqian、Wei, Shuhong、Zhong, Xiangbin

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Beijing Jiaotong Univ

Radioact Waste Proc & Disposal R&D Ctr CGN Grp

2022

10.1016/j.jnucmat.2021.153475

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.559
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