A Review of High-Temperature Characterization of Nuclear Graphites-Reference-Cited by-同舟云学术

A Review of High-Temperature Characterization of Nuclear Graphites

Published:2022-12-01 Issue: Volume: Page:80-129
ISSN:
Container-title:Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments
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Author:

Jordan Matthew S. L.¹^ORCID,Liu Dong²^ORCID,Jiang Ming²^ORCID,Tzelepi Athanasia³^ORCID

Affiliation:

1. National Nuclear Laboratory, 102 B Stonehouse Business Park, Sperry Way, Stonehouse GL10 3UT, GB

2. University of Bristol, School of Physics, Tyndall Ave., Bristol BS8 1TL, GB

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

Publisher

ASTM International

Reference101 articles.

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2. Predictions of Inter-Granular Cracking and Dimensional Changes of Irradiated Polycrystalline Graphite under Plane Strain;Delannay;Computational Materials Science,2014

3. The Generation IV International Forum, 2018, “GIF R&D; Outlook for Generation IV Nuclear Energy Systems: 2018 Update,” http://web.archive.org/web/20220302164946/https://www.gen-4.org/gif/jcms/c_196887/gif-r-d-outlook-for-generation-iv-nuclear-energy-systems-2018-update-new-cover

4. U.S. Nuclear Energy Research Advisory Committee and the Generation IV International Forum, “A Technology Roadmap for Generation IV Nuclear Energy Systems,” GIF-002-00, 2002, https://web.archive.org/web/20211208141526/https://www.gen-4.org/gif/upload/docs/application/pdf/2013-09/genivroadmap2002.pdf

5. B. Zohuri, “Generation IV Nuclear Reactors,” in Nuclear Reactor Technology Development and Utilization, ed. S. U.-D. Khan and A. Nakhabov (Sawston, UK: Woodhead Publishing, 2020), 213–246, https://doi.org/10.1016/B978-0-12-818483-7.00006-8