Corrigendum to “Accelerated materials evaluation for nuclear applications” [J. Nucl. Mater. 488 (2017) 46–62]

Journal Article · Thu Sep 21 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.09.014· OSTI ID:1395353

Griffiths, Malcolm ^[1]; Walters, L. ^[2]; Greenwood, L. R. ^[3]; Garner, F. A. ^[4]

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1. Queen's Univ., Kingston, ON (Canada)
2. Canadian Nuclear Labs., Chalk River, ON (Canada)
3. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
4. Radiation Effects Consulting, Richland, WA (United States)

The original article addresses the opportunities and complexities of using materials test reactors with high neutron fluxes to perform accelerated studies of material aging in power reactors operating at lower neutron fluxes and with different neutron flux spectra. Radiation damage and gas production in different reactors have been compared using the code, SPECTER. This code provides a common standard from which to compare neutron damage data generated by different research groups using a variety of reactors. This Corrigendum identifies a few typographical errors. Tables 2 and 3 are included in revised form.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC05-76RL01830
• OSTI ID: 1395353
• Journal Information: Journal of Nuclear Materials, Vol. 488, Issue C; Related Information: See also 10.1016/J.JNUCMAT.2017.02.039 for the original full article; ISSN 0022-3115
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS