Measurement Strategy for an Irradiated Graphite Postirradiation Examination Campaign

Author:

Wilkinson Samantha1ORCID,Shaw Tim1ORCID

Affiliation:

1. National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria CA20 1PG, GB

Publisher

ASTM International

Reference17 articles.

1. A. W. Banford, H. Eccles, and M. P. Metcalfe, “CARBOWASTE: Treatment and Disposal of Irradiated Graphite and Other Carbonaceous Waste,” https://web.archive.org/web/20210723125647/https://igdtp.eu/activity/carbowaste

2. B. J. Marsden, A. N. Jones, G. N. Hall, M. Treifi, and P. M. Mummery, “Graphite as a Core Material for Generation IV Nuclear Reactors,” in Structural Materials for Generation IV Nuclear Reactors, ed. P Yvon (Cambridge, UK: Woodhead Publishing, 2017), 495–532, https://doi.org/10.1016/B978-0-08-100906-2.00014-8

3. M. R. Bradford, “An Overview of British Energy's Graphite Core Assessment Methodology,” in Management of Ageing in Graphite Reactor Cores, ed. G. Neighbour (Cambridge, UK: RSC Publishing, 2007), 19–24, https://doi.org/10.1039/9781847557742

4. J. Reed, “Forward Strategy for Managing AGR Graphite Core Lifetime,” in The 4th EDF Energy Nuclear Graphite Symposium: Engineering Challenges Associated with the Life of Graphite Reactor Cores, ed. P. E.J. Flewitt and A. J. Wickham (Warrington, UK: EMAS Publishing, 2015), 1–20.

5. M. R. Bradford, “Reactor Inspection and Monitoring and Its Role in the Reactor Safety Case,” in The 4th EDF Energy Nuclear Graphite Symposium - Engineering Challenges Associated with the Life of Graphite Reactor Cores, ed. P. E.J. Flewitt and A. J. Wickham (Warrington, UK: EMAS Publishing, 2015), 331–340.

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1. A Review of High-Temperature Characterization of Nuclear Graphites;Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments;2022-12-01

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