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pro vyhledávání: '"Brian D. Frew"'
Autor:
Raymond M. Pace, Brian D. Frew, Hardayal S. Mehta, Hal Gustin, Anthony Giannuzzi, Katie E. Woods, Yuting Rui
Publikováno v:
Volume 6B: Materials and Fabrication.
During Refueling Outage 18 (RFO18, April 2011) Pilgrim Nuclear Power Station (PNPS) identified crack-like indications on the Steam Separator Lifting Lugs. A multi-disciplinary engineering effort was undertaken to determine the cause of the cracking a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b3f198b8b014008959c89195eb634f2
https://doi.org/10.1115/pvp2014-28091
https://doi.org/10.1115/pvp2014-28091
Publikováno v:
ASME 2010 Pressure Vessels and Piping Conference: Volume 1.
NUREG-1801, Rev. 1, Section XI.M.13, states that an ASME Code Section XI VT-3 examination is required to be performed of reactor internal components. In addition, the NUREG report specifies that for the license renewal period, these inspections shall
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1d05c005659fc7486d59c62e2e832ae9
https://doi.org/10.1115/pvp2010-25974
https://doi.org/10.1115/pvp2010-25974
Publikováno v:
British Journal of Special Education; Sep1986, Vol. 13 Issue 3, p125-125, 1p
Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for th
