Small-Specimen Testing, with Image-Based Analysis, for Crack Propagation Resistance in Polygranular Nuclear Graphite-Reference-Cited by-同舟云学术

Small-Specimen Testing, with Image-Based Analysis, for Crack Propagation Resistance in Polygranular Nuclear Graphite

Published:2022-12-01 Issue: Volume: Page:1-17
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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:

Marrow James¹,Scotson Dan¹,Jin Xiaochao¹²,Chen Hongniao¹³,Chen Yang¹⁴,Koko Abdo¹,Earp Philip¹⁵,Wu Houzheng⁶

Affiliation:

1. Dept. of Materials, Oxford University, Parks Rd., Oxford OX1 3PH, GB

2. State Key Laboratory for Strength and Vibration of Mechanical Structures, School of Aerospace Engineering, Xi’an Jiaotong University, Xi’an 710049, CN

3. Space Structures Research Center, Guizhou University, Guiyang 550003, CN

4. Dept. of Mechanical Engineering, University of Bath, North Rd, Claverton Down BA2 7AY, GB

5. Culham Science Centre, UKAEA Culham, Abingdon OX14 3EB, GB

6. Dept. of Materials, Loughborough University, Epinal Way, Loughborough LE11 3TU, GB

Publisher

ASTM International

Reference83 articles.

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2. Graphite—the Most Fascinating Nuclear Material;Kelly;Carbon,1982

3. The Mechanical Properties of Reactor Graphite;Taylor;Carbon,1967

4. B. J. Marsden and G. N. Hall, “Graphite in Gas-Cooled Reactors,” in Comprehensive Nuclear Materials, vol. 4, ed. Rudy J. M.Konings (Amsterdam, The Netherlands: Elsevier, 2012), 325–390, https://doi.org/10.1016/B978-0-08-056033-5.00092-6

5. Recommendations for a Restart of Molten Salt Reactor Development;Moir;Energy Conversion and Management,2008

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2. 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