Zobrazeno 1 - 7
of 7
pro vyhledávání: '"Kawaljit Ahluwalia"'
Autor:
Gary L. Stevens, Junjie Chen, Kawaljit Ahluwalia, Changheui Jang, Ho-Sub Kim, Tae Soon Kim, Hyeon Bae Lee
Publikováno v:
Corrosion Science. 151:97-107
In a simulated pressurized water reactor (PWR) environment with 30 ppb of Zn and peak holding, the low-cycle fatigue (LCF) life of 316 SS increased about 3 times compared to that without them. For the specimens tested with Zn and strain holding, the
Publikováno v:
Volume 1: Codes and Standards.
To further understand the environmentally assisted fatigue (EAF) behavior of Type 316 austenitic stainless steels (SS) in a pressurized water reactor (PWR) primary water environment, the influence of non-isothermal transient conditions was investigat
Autor:
Gary L. Stevens, Kawaljit Ahluwalia, Junjie Chen, Ho-Sub Kim, Tae Soon Kim, Hyeon Bae Lee, Changheui Jang
Publikováno v:
Volume 1: Codes and Standards.
Low cycle fatigue (LCF) tests of type 316 stainless steel (SS) were conducted in simulated pressurized water reactor (PWR) environments to evaluate the effect of zinc (Zn) content and peak strain holding. The LCF lives of 316 SS increased about 2 to
Publikováno v:
The Minerals, Metals & Materials Series ISBN: 9783030046385
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::564c06a3d52649dd3bc61dcb93e53f45
https://doi.org/10.1007/978-3-030-04639-2_3
https://doi.org/10.1007/978-3-030-04639-2_3
Autor:
Seiji Asada, Daiki Takagoshi, Yuichi Fukuta, Kazuya Tsutsumi, Kawaljit Ahluwalia, David Steininger
Publikováno v:
Volume 1A: Codes and Standards.
In order to understand the fatigue behavior in PWR primary water environment, the influence of non-isothermal transient condition was investigated for austenitic stainless steel 316SS. In our previous study (PVP2016-63798), isothermal and non-isother
Publikováno v:
Volume 1A: Codes and Standards.
To understand the fatigue behavior of austenitic stainless steels in a simulated PWR primary water environment, the patterns were studied. Austenitic stainless steel Type 316 plate was used as the test material. Regarding non-isothermal testing: isot
Publikováno v:
Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors ISBN: 9783319487601
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors
Alloy 690 base metal, HAZ and weld metal were tested in representative PWR primary water at 290 to 360°C. Intergranular cracking was observed in all materials. Growth rates as high as 1.2 × 10−6 mm/s were observed in the S-L orientation with micr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f39295322e8c2503e613759873335ce3
https://doi.org/10.1002/9781118456835.ch19
https://doi.org/10.1002/9781118456835.ch19