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This content will become publicly available on September 21, 2018

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

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.
Authors:
 [1] ;  [2] ;  [3] ;  [4]
  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)
Publication Date:
Grant/Contract Number:
AC05-76RL01830
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 488; Journal Issue: C; Related Information: See also 10.1016/J.JNUCMAT.2017.02.039 for the original full article; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
OSTI Identifier:
1395353