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Publikováno v:
Corrosion; Jan2015, Vol. 71 Issue 1, p57-64, 8p
Publikováno v:
Corrosion; Dec2007, Vol. 63 Issue 12, p1114-1123, 10p, 6 Diagrams, 2 Charts, 5 Graphs
Publikováno v:
Corrosion; Aug2015, Vol. 71 Issue 8, p1027-1035, 9p
Publikováno v:
CORROSION. 71:1027-1035
The primary water stress corrosion cracking (PWSCC) susceptibility of Ni-based alloys, such as Alloy 600 (UNS N06600), has been much higher than that of Fe-based alloys, such as Type 316 stainless steel (UNS S31600). This phenomenon is generally reco
Publikováno v:
CORROSION. 63:1114-1123
The rate of stress corrosion cracking (SCC) was measured for nonsensitized, cold-worked Type 316 (UNS S31600) and Type 304 (UNS S30400) in both hydrogenated pressurized water reactor (PWR)...
Autor:
Warren H. Bamford, David M. Moon
Publikováno v:
CORROSION. 36:289-298
The fatigue crack growth behavior of A533B and A508 pressure vessel steel and Types 304 and 316 steels used in reactor coolant piping has been studied in a pressurized water reactor environment at 288 C (550 F). The influence of stress ratio (Pmin/Pm
Autor:
Fred F. Lyle
Publikováno v:
CORROSION. 29:86-94
This paper describes tests conducted on samples of Type 304 tubing from which fuel cladding in the replacement core for the Nuclear Ship Savannah was manufactured. The major objective of the tests was to determine if exposed nonmetallic inclusions in
Publikováno v:
Corrosion. 25:194-198
Corrosion tests were run for periods up to 5000 hrs in borated water at 600 F (316 C) in a high velocity loop on strip, tubes, and weldments of Alloy 600. During the first 1000 to 2000 hrs of exposure, corrosion rate differences depending upon surfac