Electrochemical decontamination of irradiated nuclear graphite from corrosion and fission products using molten salt-Reference-Cited by-同舟云学术

Electrochemical decontamination of irradiated nuclear graphite from corrosion and fission products using molten salt

Published:2021 Issue:10 Volume:14 Page:5501-5512
ISSN:1754-5692
Container-title:Energy & Environmental Science
language:en
Short-container-title:Energy Environ. Sci.

Author:

Grebennikova Tatiana¹²^ORCID,Jones Abbie N.²^ORCID,Sharrad Clint A.¹^ORCID

Affiliation:

1. Department of Chemical Engineering and Analytical Science, School of Engineering, The University of Manchester, Oxford Road, Manchester, M13 9PL, UK

2. The Nuclear Graphite Research Group (NGRG), Department of Mechanical, Aeronautical and Civil Engineering, School of Engineering, The University of Manchester, Oxford Road, Manchester, M13 9PL, UK

Abstract

A treatment method for nuclear graphite has been developed that removes the majority of multiple contaminants, reducing nuclear waste volumes.

Funder

Nuclear Decommissioning Authority

University of Manchester

Publisher

Royal Society of Chemistry (RSC)

Subject

Pollution,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment,Environmental Chemistry

Link

http://pubs.rsc.org/en/content/articlepdf/2021/EE/D1EE00332A

Reference82 articles.

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3. U. S. Atomic Energy Commission, The first reactor , U.S. Atomic Energy Commission, Division of Technical Information , 1968

4. International Atomic Energy Agency, Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors , IAEA-Tecdoc 1521 , IAEA, Vienna , 2006

5. Graphite as a neutron moderator and reflector material

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