Zobrazeno 1 - 10
of 30
pro vyhledávání: '"G. P. Wozadlo"'
Publikováno v:
CORROSION. 51:731-737
Low-temperature (400°C to 500°C) annealing (LTA) treatments were conducted on type 304 (UNS S30400) stainless steel (SS) that had been irradiated to fast neutron fluences from 1.74 × 1021 n/cm2 to 2.95 × 1021 n/cm2 (E [energy] > 1 MeV). The purpo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::87fe71f790c57ad7b83c3a19aee998ec
https://doi.org/10.5006/1.3293549
https://doi.org/10.5006/1.3293549
Publikováno v:
CORROSION. 49:650-655
A constant deflection test was developed to evaluate the susceptibility of irradiated stainless steel (SS) to irradiation-assisted stress corrosion cracking. The test was shown useful in supplementing constant extension rate tensile or slow strain ra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ecaa1788dff056621ad75168da6b9da
https://doi.org/10.5006/1.3316096
https://doi.org/10.5006/1.3316096
Publikováno v:
CORROSION. 49:145-155
Constant load stress corrosion tests were conducted on type 304 SS, which had been irradiated to fast neutron fluences in the range from 0.12 to 3.00 × 1021 n/cm2 (E> 1 MeV) in two boiling water reactors. The material originated from three different
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8acdaaf960973aa1baee91089c29430f
https://doi.org/10.5006/1.3299209
https://doi.org/10.5006/1.3299209
Autor:
A. J. Jacobs, G. P. Wozadlo
Publikováno v:
Journal of Materials Engineering. 9:345-351
Irradiation-assisted stress corrosion cracking (IASCC) is a form of intergranular stress corrosion cracking (IGSCC) that has occurred infrequently during the last two decades in in-core components of nonsensitized austenitic stainless steel. IASCC is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9ac132294b0c087828c5c6e4e6972583
https://doi.org/10.1007/bf02834045
https://doi.org/10.1007/bf02834045
Autor:
W. L. Pearl, G. P. Wozadlo
Publikováno v:
Corrosion. 21:260-267
Results are reported for the continuation1 of extensive corrosion testing of carbon steel exposed in a dynamic test loop simulating the various environments found in a nuclear boiling-water-reactor system. Water and steam conditions were based on 20
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c86b299f26b916cd847f66f446fdd4dd
https://doi.org/10.5006/0010-9312-21.8.260
https://doi.org/10.5006/0010-9312-21.8.260
Autor:
Rebak, Raul
Publikováno v:
Metallurgical & Materials Transactions. Part E; Dec2015, Vol. 2 Issue 4, p197-207, 11p
Publikováno v:
Energy Materials 2014; 2014, p431-442, 11p
Publikováno v:
Strength of Materials; Mar2012, Vol. 44 Issue 2, p115-128, 14p
Publikováno v:
Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors; 1999, p477-484, 8p