Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Kuk‐cheol Kim"'
Publikováno v:
Journal of Pressure Vessel Technology. 145
In order to ensure the integrity of structures such as gas turbines and nuclear power plants, the materials used should have excellent toughness. Especially in the case of nuclear piping materials applied to leak before break (LBB) design, high tough
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5215ee3110f5d275ef18c24f0217fef5
https://doi.org/10.1115/1.4055089
https://doi.org/10.1115/1.4055089
Publikováno v:
Materials Research Innovations. 17:332-336
One of the main mechanisms of turbine rotor damage is cyclic thermal stress produced during transition conditions, such as warm-up and shutdown processes. In this paper, the cyclic damage with ramp rate is studied in terms of material properties. To
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::badb4dc805391b5f61ec7dd97552e9ad
https://doi.org/10.1179/1432891713z.000000000252
https://doi.org/10.1179/1432891713z.000000000252
Publikováno v:
Advanced Science Letters. 4:2555-2559
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::679d997b8d9d9e92eb921a256bf0cbf5
https://doi.org/10.1166/asl.2011.1696
https://doi.org/10.1166/asl.2011.1696
Publikováno v:
Advanced Materials Research. :1141-1144
The demand for ultra supercritical (USC) power plants has increased due to the need for high thermal efficiency and reduced CO2 emissions. For turbine materials, high-cycle and lowcycle fatigue life at USC service temperatures are needed to verify ma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd7b5abb5d2392e36f2e9e3a428b2ee6
https://doi.org/10.4028/www.scientific.net/amr.26-28.1141
https://doi.org/10.4028/www.scientific.net/amr.26-28.1141
Publikováno v:
Nuclear Power-Control, Reliability and Human Factors
Because safety is of paramount importance in the nuclear industry, numerous efforts have been made to guarantee structural integrity against sudden accidents. In the past, design against a Double Ended Guillotine Break (DEGB) was accomplished through
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::badac20785271ffdb283fc5dd2444495
http://www.intechopen.com/articles/show/title/evaluation-of-dynamic-j-r-curve-for-leak-before-break-design-of-nuclear-reactor-coolant-piping-syste
http://www.intechopen.com/articles/show/title/evaluation-of-dynamic-j-r-curve-for-leak-before-break-design-of-nuclear-reactor-coolant-piping-syste
Publikováno v:
Fatigue of Materials: Advances and Emergences in Understanding
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3752213342c4ba14bf78d03c4484d121
https://doi.org/10.1002/9781118013373.ch14
https://doi.org/10.1002/9781118013373.ch14
Publikováno v:
Volume 6: Materials and Fabrication, Parts A and B.
The test method for the reliability of this research dynamic J-R curve for long crack extension based on normalization method was introduced on this research. For nuclear power plant piping material made of ferritic steel, dynamic J-R curve is one of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88edc1beadfeaccd70c73274d3af7d2b
https://doi.org/10.1115/pvp2009-77069
https://doi.org/10.1115/pvp2009-77069
Publikováno v:
Volume 6: Materials and Fabrication.
Nuclear power plants have been operated for fifty years. Currently the managements of spent fuel are on progress vigorously. Casks for transportation and/or storage of spent nuclear fuel are usually made of SA350 low alloy steels. The wall thickness
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fb3bc9b225061e43ca2cb94be44b03bd
https://doi.org/10.1115/pvp2007-26530
https://doi.org/10.1115/pvp2007-26530
Publikováno v:
Application of Fracture Mechanics in Failure Assessment.
In order to apply leak before break (LBB) design for nuclear primary piping systems, dynamic and static J-R tests of field fabrication weld metal were carried out to determine mechanical properties at 316°C. For the reactor coolant piping system mad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7643118fe3eebc8942eca3c83d67eb45
https://doi.org/10.1115/pvp2003-2011
https://doi.org/10.1115/pvp2003-2011