Simulated advanced gas-cooled reactor spent nuclear fuels: Determination of the O/U ratio - an XRD, XPS and Raman study-Reference-Cited by-同舟云学术

Simulated advanced gas-cooled reactor spent nuclear fuels: Determination of the O/U ratio - an XRD, XPS and Raman study

Published:2022-09 Issue: Volume:568 Page:153867
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Wilbraham Richard J.^ORCID,Howett Elizabeth A.,Boxall Colin,Hambley David I.,Higgins Jessica K.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference120 articles.

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3. Department of Energy and Climate Change, Implementing Geological disposal: A Framework For the Long-Term Management of Higher Activity Radioactive Waste. URN 14D/235, 1–54. 2014. UK Government.

4. UK Spent Fuel Research Group-http://snf.esc.cam.ac.uk/. 2017. 20-2-2017.

5. Multicycle reprocessing and refabrication experiments on sintered UO2-fissia pellets;Strausberg;Ind. Eng. Chem. Process Design Develop.,1963

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