Assessment of void swelling in austenitic stainless steel core internals / prepared by H.M. Chung
- Chung, H. M.
- Washington, DC : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 2006.
- Physical Description:
- xiv, 24 pages : digital, PDF file
- Additional Creators:
- U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology and Argonne National Laboratory
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Title from title screen (viewed on Aug. 19, 2008)., "Argonne National Laboratory.", "January 2006.", "NUREG/CR-6897.", and "ANL-04/28."
- Technical Details:
- Mode of access: Internet from the NRC web site. Address as of 8/19/08: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6897/cr6897.pdf; current access available via PURL.
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